IR 05000285/2016003: Difference between revisions

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SUBJECT: FORT CALHOUN STATION  
SUBJECT: FORT CALHOUN STATION  
- NRC INTEGRATED INSPECTION REPORT NUMBER 05000285/
- NRC INTEGRATED INSPECTION REPORT NUMBER 05000285/2016003
2016003


==Dear Mr. Marik:==
==Dear Mr. Marik:==
On September 30, 201 6, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Fort Calhoun Station.
O n September 30, 201 6 , the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Fort Calhoun Station.


On October 12, 2016, the NRC inspectors discussed the results of this inspection with Michael J. Prospero, Acting Site Vice President, and other members of your staff.
O n October 12, 2016, the NRC inspectors discussed the results of this inspection with Michael J. Prospero, Acting Site Vice President, and other members of your staff.


The results of this inspection are documented in the enclosed report
The results of this inspection are documented in the enclosed report
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1. Supplemental Information 2. Request for Information for the Occupational/Public Radiation Safety Inspection
1. Supplemental Information 2. Request for Information for the Occupational/Public Radiation Safety Inspection


SUNSI Review By: GMiller ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: NRC-002 OFFICE SRI:DRP/D RI:DRP/D C:DRS/EB1 C:DRS/EB2 C:DRS/OB C:DRS/PSB2 TL:IPAT NAME MSchneider LBrandt TFarnholtz GWerner VGaddy HGepford THipschman SIGNATURE
SUNSI Review By: GMiller ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: NRC-002 OFFICE SRI:DRP/D RI:DRP/D C:DRS/EB1 C:DRS/EB2 C:DRS/OB C:DRS/PSB2 TL:IPAT NAME MSchneider LBrandt TFarnholtz GWerner VGaddy HGepford THipschman SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 10/14/16 10/18/16 10/14/16 10/14/16 10/18/16 10/18/16 10/25/16 OFFICE BC:DRP/D NAME GMiller SIGNATURE /RA/ DATE 11/9/16 Letter to Shane from Geoffrey B. Miller dated November 8, 2016
/RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 10/14/16 10/18/16 10/14/16 10/14/16 10/18/16 10/18/16 10/25/16 OFFICE BC:DRP/D NAME GMiller SIGNATURE
/RA/ DATE 11/9/16 Letter to Shane from Geoffrey B. Miller dated November 8, 2016


SUBJECT: FORT CALHOUN STATION  
SUBJECT: FORT CALHOUN STATION  
- NRC INTEGRATED INSPECTION REPORT NUMBER 05000285/2016003 DISTRIBUTION
- NRC INTEGRATED INSPECTION REPORT NUMBER 05000285/2016003 DISTRIBUTION
: Regional Administrator (Kriss.Kennedy@nrc.gov)
: Regional Administrator (Kriss.Kennedy@nrc.gov) Deputy Regional Administrator (Scott.Morris@nrc.gov) DRP Director (Troy.Pruett@nrc.gov)
Deputy Regional Administrator (Scott.Morris@nrc.gov) DRP Director (Troy.Pruett@nrc.gov)
DRP Deputy Director (Ryan.Lantz@nrc.gov
DRP Deputy Director (Ryan.Lantz@nrc.gov
) DRS Director (Anton.Vegel@nrc.gov)
) DRS Director (Anton.Vegel@nrc.gov)
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Acting Resident Inspector (Shawn.Money@nrc.gov
Acting Resident Inspector (Shawn.Money@nrc.gov
) Acting Resident Inspector (Thomas.Sullivan@nrc.gov)
) Acting Resident Inspector (Thomas.Sullivan@nrc.gov)
Acting Resident Inspector (Lindsay.Brandt@nrc.gov) Acting Site Administrative Assistant (Amy.Elam@nrc.gov)
Acting Resident Inspector (Lindsay.Brandt@nrc.gov) Acting Site Administrative Assistant (Amy.Elam@nrc.gov) Branch Chief, DRP/D (Geoffrey.Miller@nrc.gov) Senior Project Engineer, DRP/E (John.Dixon@nrc.gov)
Branch Chief, DRP/D (Geoffrey.Miller@nrc.gov)
Senior Project Engineer, DRP/E (John.Dixon@nrc.gov)
Project Engineer, DRP/D (Jim.Melfi@nrc.gov
Project Engineer, DRP/D (Jim.Melfi@nrc.gov
) Project Engineer, DRP/D (Brian.Parks@nrc.gov)
) Project Engineer, DRP/D (Brian.Parks@nrc.gov)
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RIV RSLO (Bill.Maier@nrc.gov)
RIV RSLO (Bill.Maier@nrc.gov)
ACES (R4Enforcement.Resource@nrc.gov)
ACES (R4Enforcement.Resource@nrc.gov)
ROPreports.Resource@nrc.gov ROPassessment.Resource@nrc.gov Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000285 License: DPR-40 Report: 05000285/201600 3 Licensee:
ROPreports.Resource@nrc.gov ROPassessment.Resource@nrc.gov Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000285 License: DPR-40 Report: 05000285/201600 3 Licensee: Omaha Public Power District Facility: Fort Calhoun Station Location: 9610 Power Lane Blair, NE 68008 Dates: July 1 through September 30, 2016 Inspectors:
Omaha Public Power District Facility:
Fort Calhoun Station Location:
9610 Power Lane Blair, NE 68008 Dates: July 1 through September 30, 2016 Inspectors:
S. Schneider, Senior Resident Inspector S. Money, Acting Resident Inspector T. Sullivan, Acting Resident Inspector L. Brandt, Acting Resident Inspector L. Carson II, Sr. Health Physicist N. Greene, PhD, Health Physicist P. Hernandez, Health Physicist J. Kirkland, Senior Operations Engineer J. O'Donnell, CHP, Health Physicist C. Cowdrey, Operations Engineer Approved By: Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects  
S. Schneider, Senior Resident Inspector S. Money, Acting Resident Inspector T. Sullivan, Acting Resident Inspector L. Brandt, Acting Resident Inspector L. Carson II, Sr. Health Physicist N. Greene, PhD, Health Physicist P. Hernandez, Health Physicist J. Kirkland, Senior Operations Engineer J. O'Donnell, CHP, Health Physicist C. Cowdrey, Operations Engineer Approved By: Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects  


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IR 05000285/2016003
IR 05000285/2016003


; 07/01/2016  
; 0 7/01/2016 - 0 9/30/2016; Fort Calhoun Station
- 09/30/2016; Fort Calhoun Station
; Integrated Inspection Report. The inspection activities described in this report were performed between July 1 and September 30 , 2016 , by the resident inspectors at Fort Calhoun Station and inspectors from the NRC's Region IV office. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process."
; Integrated Inspection Report. The inspection activities described in this report were performed between July 1 and September 30, 2016, by the resident inspectors at Fort Calhoun Station and inspectors from the NRC's Region IV office
. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process."


No findings were identified.
No findings were identified.


==PLANT STATUS==
=PLANT STATUS=
The unit began the inspection period at approximately 98 percent power following start-up from an unplanned automatic reactor trip and returned to 100 percent power on July 1, 2016. On September 29, 2016, the licensee commenced a power coastdown
 
The unit began the inspection period at approximately 98 percent power following start
-up from an unplanned automatic reactor trip and returned to 100 percent power on July 1, 2016. On September 29 , 2016, the licensee commenced a power coastdown
, and Fort Calhoun operated at approximately 98.5 percent power at the end of the inspection period.
, and Fort Calhoun operated at approximately 98.5 percent power at the end of the inspection period.


=REPORT DETAILS=
REPORT DETAILS


==REACTOR SAFETY==
==REACTOR SAFETY==
Cornerstones:  Initiating Events, Mitigating Systems, and Barrier Integrity
Cornerstones:  Initiating Events, Mitigating Systems, an d Barrier Integrity 1 R 01 Adverse Weather Protection (71111.01)
{{a|1R01}}
==1R01 Adverse Weather Protection==
{{IP sample|IP=IP 71111.01}}
Readiness for Impending Adverse Weather Conditions
Readiness for Impending Adverse Weather Conditions


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-related equipment
-related equipment
. The inspectors evaluated operator staffing and accessibility of controls and indications for those systems required to control the plant and conducted a plant walk
. The inspectors evaluated operator staffing and accessibility of controls and indications for those systems required to control the plant and conducted a plant walk
-down. These activities constitute d one sample of readiness for impending adverse weather condition s, as defined in Inspection Procedure 71111.01.
-down. These activities constitute d one sample of readiness for impending adverse weather condition s , as defined in Inspection Procedure 71111.01.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R04}}
 
==1R04 Equipment Alignment==
1 R 04 Equipment Alignment (71111.04)
{{IP sample|IP=IP 71111.04}}
 
===.1 Partial Walk===
===.1 Partial Walk===


Line 130: Line 118:
====a. Inspection Scope====
====a. Inspection Scope====
The inspectors performed partial system walk
The inspectors performed partial system walk
-downs of the following risk-significant systems:  July 13, 2016, emergency diesel generator 2 during testing on emergency diesel generator 1  July 18, 2016, steam driven auxiliary feedwater pump FW-10 prior to motor driven auxiliary feedwater pump FW-6 operability test  September 20, 2016, auxiliary feedwater system prior to steam driven auxillary feedwater pump FW-10 operability test September 26, 2016, component cooling water system with component cooling water pump AC-3B out of service for maintenance The inspectors reviewed the licensee's procedures and system design information to determine the correct lineup for the systems. They visually verified that critical portions of the systems were correctly aligned for the existing plant configuration
-downs of the following risk-significant systems:  July 13, 2016, emergency diesel generator 2 during testing on emergency diesel generator 1  July 18, 2016, steam driven auxiliary feedwater pump FW-10 prior to motor driven auxiliary feedwater pump FW-6 operability test  September 20, 2016, auxiliary feedwater system prior to steam driven auxillary feedwater pump FW-10 operability test September 26, 2016, component cooling water system with component cooling water pump AC-3 B out of service for maintenance The inspectors reviewed the licensee's procedures and system design information to determine the correct lineup for the systems. They visually verified that critical portions of the systems were correctly aligned for the existing plant configuration
. These activities constitute d four partial system walk
. These activities constitute d four partial system walk
-down samples as defined i n Inspection Procedure 71111.04.
-down samples a s defined i n Inspection Procedure 71111.04.


====b. Findings====
====b. Findings====
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The inspectors then visually verified that the system was correctly aligned for the existing plant configuration.
The inspectors then visually verified that the system was correctly aligned for the existing plant configuration.


These activities constitute d one complete system walk
These activities constitute d o ne complete system walk
-down sample
-down sample , as defined in Inspection Procedure 71111.04.
, as defined in Inspection Procedure 71111.04.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R05}}
 
==1R05 Fire Protection==
1 R 05 Fire Protection (71111.05)
{{IP sample|IP=IP 71111.05}}
Quarterly Inspection
Quarterly Inspection


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors evaluated the licensee's fire protection program for operational status and material condition. The inspectors focused their inspection on five plant areas important to safety
The inspectors evaluated the licensee's fire protection program for operational status and material condition. The inspectors focused their inspection on five plant areas important to safety
:  July 21, 2016, emergency diesel generator room 1, fire area 35A August 10, 2016, auxiliary building, fire area August 10, 2016, auxiliary building, fire area August 11, 2016, auxiliary building, fire areas 35A and 35B  August 12, 2016, auxiliary building, fire area For each area, the inspectors evaluated the fire plan against defined hazards and defense-in-depth features in the licensee's fire protection program. The inspectors evaluated control of transient combustibles and ignition sources, fire detection and suppression systems, manual firefighting equipment and capability, passive fire protection features, and compensatory measures for degraded conditions.
:  July 21, 2016, emergency diesel generator room 1, fire area 35 A August 10, 2016, auxiliary building, fire area August 10, 2016, auxiliary building, fire area August 11, 2016, auxiliary building, fire areas 35A an d 35B  August 12, 2016, auxiliary building, fire area For each area, the inspectors evaluated the fire plan against defined hazards and defense-in-depth features in the licensee's fire protection program. The inspectors evaluated control of transient combustibles and ignition sources, fire detection and suppression systems, manual firefighting equipment and capability, passive fire protection features, and compensatory measures for degraded conditions.


These activities constitute d five quarterly inspection sample s, as defined in Inspection Procedure 71111.05.
These activities constitute d five quarterly inspection sample s , as defined in Inspection Procedure 71111.05.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R06}}
 
==1R06 Flood Protection Measures==
1 R 06 Flood Protection Measures (71111.06)
{{IP sample|IP=IP 71111.06}}


====a. Inspection Scope====
====a. Inspection Scope====
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====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R07}}
 
==1R07 Heat Sink Performance==
1 R 07 Heat Sink Performance (71111.07)
{{IP sample|IP=IP 71111.07}}


====a. Inspection Scope====
====a. Inspection Scope====
On August 15, 2016
On August 15, 2016 , the inspectors completed an inspection of the readiness and availability of a risk-significant heat exchanger. The inspectors reviewed the data from the performance of spent fuel pool cooling heat exchanger AC-8 disassembly, cleaning, visual inspection, and reassembly activities.
, the inspectors completed an inspection of the readiness and availability of a risk-significant heat exchanger. The inspectors reviewed the data from the performance of spent fuel pool cooling heat exchanger AC-8 disassembly, cleaning, visual inspection, and reassembly activities.


Additionally, the inspectors walked down spent fuel pool cooling heat exchanger AC-8 to observe its performance and material condition and verified that the heat exchanger was correctly categorized under the Maintenance Rule and was receiving the required maintenance.
Additionally, the inspectors walked down spent fuel pool cooling heat exchanger AC-8 to observe its performance and material condition and verified that the heat exchanger was correctly categorized under the Maintenance Rule and was receiving the required maintenance.


These activities constitute d completion of one heat sink performance annual review sample, as defined in Inspection Procedure 71111.07.
These activities constitute d completion of one heat sink performance annual review sample , as defined in Inspection Procedure 71111.07.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R11}}
 
==1R11 Licensed Operator Requalification Program and Licensed Operator Performance==
1 R 11 Licensed Operator Requalification Program and Licensed Operator Performance (71111.11)
{{IP sample|IP=IP 71111.11}}
 
===.1 Review of Licensed Operator Requalification===
===.1 Review of Licensed Operator Requalification===


====a. Inspection Scope====
====a. Inspection Scope====
On July 26, 2016, the inspectors observed an Emergency Plan drill for an operating crew in the simulator. The inspectors assessed the performance of the operators and the evaluators' critique of their performance. The inspectors also assessed the modeling and performance of the simulator during the requalification activities
On July 26, 2016, the inspectors observed an Emergency Plan drill for an operating crew in the simulator. The inspectors assessed the performance of the operators and the evaluators' critique of their performance. The inspectors also assessed the modeling and performance of the simulator during the requalification activities
. These activities constitute d completion of one quarterly licensed operator requalification program sample
. These activities constitute d completion of one quarterly licensed operator requalification program sample , as defined in Inspection Procedure 71111.11.
, as defined in Inspection Procedure 71111.11.


====b. Findings====
====b. Findings====
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The inspectors observed the operators' performance of the following activities:
The inspectors observed the operators' performance of the following activities:
July 5, 2016, operators responded to an automatic isolation of steam generator B blowdown  August 10, 2016
July 5, 2016, operators responded to an automatic isolation of steam generator B blowdown  August 10, 2016 , entry into abnormal operating procedure AOP-31 due to 161 k V grid disturbance s  August 29, 2016, entry into abnormal operating procedure AOP-12 due to loss of containment integrity September 13, 2016, operators performed an emergency diesel generator 1 surveillance test while conducting fuel moves in the spent fuel pool and diluting the reactor coolant system September 15, 2016, operators respond ed to the failed Loop 2 T hot resistance temperature detector from the B reactor protective system instrument channel In addition, the inspectors assessed the operators' adherence to plant procedures and other operations department policies.
, entry into abnormal operating procedure AOP-31 due to 161 kV grid disturbance s  August 29, 2016, entry into abnormal operating procedure AOP-12 due to loss of containment integrity September 13, 2016, operators performed an emergency diesel generator 1 surveillance test while conducting fuel moves in the spent fuel pool and diluting the reactor coolant system September 15, 2016, operators respond ed to the failed Loop 2 Thot resistance temperature detector from the B reactor protective system instrument channel In addition, the inspectors assessed the operators' adherence to plant procedures and other operations department policies.


These activities constitute d completion of five quarterly licensed operator performance samples, as defined in Inspection Procedure 71111.11.
These activities constitute d completion of five quarterly licensed operator performance sample s , a s defined in Inspection Procedure 71111.11.


====b. Findings====
====b. Findings====
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Two individuals failed the written examinations. One individual was remediated, retested, and passed their retake examination. The other individual was remediated, retested, and failed their retake examination. On September 26, 2016, the licensee requested that this individual's license be terminated.
Two individuals failed the written examinations. One individual was remediated, retested, and passed their retake examination. The other individual was remediated, retested, and failed their retake examination. On September 26, 2016, the licensee requested that this individual's license be terminated.


The inspectors observed examination security measures in place during administration of the examinations (including controls and content overlap) and reviewed any remedial training and re
The inspectors observed examination security measures in place during administration of the examinatio ns (including controls and content overlap) and reviewed any remedial training and re
-examinations, if necessary. The inspectors also reviewed medical records of five licensed operators for conformance to license conditions and the licensee's system for tracking qualifications and records of license reactivation for one operator.
-examinations, if necessary. The inspectors also reviewed medical records of five licensed operators for conformance to license conditions and the licensee's system for tracking qualifications and records of license reactivation for one operator.


Line 242: Line 223:
====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R12}}
 
==1R12 Maintenance Effectiveness==
1 R 12 Maintenance Effectiveness (71111.12)
{{IP sample|IP=IP 71111.12}}


====a. Inspection Scope====
====a. Inspection Scope====
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-related structures, systems, and components (SSCs):  July 28, 2016, spent fuel pool bridge failure The inspectors reviewed the extent of condition of possible common cause SSC failures and evaluated the adequacy of the licensee's corrective actions. The inspectors reviewed the licensee's work practices to evaluate whether these may have played a role in the degradation of the SSCs. The inspectors assessed the licensee's characterization of the degradation in accordance with 10 CFR 50.65 (the Maintenance Rule), and verified that the licensee was appropriately tracking degraded performance and conditions in accordance with the Maintenance Rule.
-related structures, systems, and components (SSCs):  July 28, 2016, spent fuel pool bridge failure The inspectors reviewed the extent of condition of possible common cause SSC failures and evaluated the adequacy of the licensee's corrective actions. The inspectors reviewed the licensee's work practices to evaluate whether these may have played a role in the degradation of the SSCs. The inspectors assessed the licensee's characterization of the degradation in accordance with 10 CFR 50.65 (the Maintenance Rule), and verified that the licensee was appropriately tracking degraded performance and conditions in accordance with the Maintenance Rule.


These activities constitute d completion of one maintenance effectiveness sample, as defined in Inspection Procedure 71111.12.
These activities constitute d completion of one maintenance effectiveness sample , a s defined in Inspection Procedure 71111.12.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R13}}
 
==1R13 Maintenance Risk Assessments and Emergent Work Control==
1 R 13 Maintenance Risk Assessments and Emergent Work Control (71111.13)
{{IP sample|IP=IP 71111.13}}


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors reviewed two risk assessments performed by the licensee prior to changes in plant configuration and the risk management actions taken by the licensee in response to elevated risk:
The inspectors reviewed two risk assessments performed by the licensee prior to changes in plant configuration and the risk management actions taken by the licensee in response to elevated risk:
July 8, 2016, planned yellow risk during emergency diesel generator 2 maintenance August 17, 2016, planned yellow risk during emergency diesel generator 1 testing The inspectors verified that these risk assessment s were performed timely and in accordance with the requirements of 10 CFR 50.65 (the Maintenance Rule) and plant procedures. The inspectors reviewed the accuracy and completeness of the licensee's risk assessments and verified that the licensee implemented appropriate risk management actions based on the result of the assessments
July 8, 2016, planned yellow risk during emergency diesel generator 2 maintenance August 17, 2016, planned yellow risk during emergency diesel generator 1 testing The inspectors verified that these risk assessment s were performed timely and in accordance with the requirements of 10 CFR 50.65 (the Maintenance Rule) and plant procedures. The inspectors reviewed the accuracy and completeness of the licensee's risk assessments and verified that the licensee implemented appropriate risk management actions based on the result of the assessments
. These activities constitute d completion of two maintenance risk assessment inspection samples, as defined in Inspection Procedure 71111.13.
. These activities constitute d completion of two maintenance risk assessment inspection samp le s , as defined in Inspection Procedure 71111.13.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R15}}
==1R15 Operability Determinations==


and Functionality Assessments (71111.15)
1 R 15 Operability Determinations and Functionality Assessments (71111.15)


====a. Inspection Scope====
====a. Inspection Scope====
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These activities constitute d completion of six operability review samples, which included one operator work
These activities constitute d completion of six operability review samples, which included one operator work
-around sample, as defined in Inspection Procedure 71111.15.
-around sample, a s defined in Inspection Procedure 71111.15.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R18}}
 
==1R18 Plant Modifications==
1 R 18 Plant Modifications (71111.18)
{{IP sample|IP=IP 71111.18}}


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors reviewed two temporary plant modifications that affected risk
The inspectors reviewed two temporary plant modifications that affected risk
-significant structures, systems, and components (SSCs):
-significant structures, systems, and components (SSCs):
August 24, 2016, tornado protection for raw water system cable pull boxes September 23, 2016, removal of a failed Loop 2 Thot resistance temperature detector from the B reactor protecti ve system instrument channel The inspectors verified that the licensee had installed these temporary modifications in accordance with technically adequate design documents. The inspectors verified that these modifications did not adversely impact the operability or availability of affected SSCs. The inspectors reviewed design documentation and plant procedures affected by the modifications to verify the licensee maintained configuration contro l. These activities constitute d completion of two samples of temporary modifications, as defined in Inspection Procedure 71111.18.
August 24, 2016, tornado protection for raw water system cable pull boxes September 23, 2016, removal of a failed Loop 2 T ho t resistance temperature detector from the B reactor protecti ve system instrument channel The inspectors verified that the licensee had installed these temporary modifications in accordance with technically adequate design documents. The inspectors verified that these modifications did not adversely impact the operability or availability of affected SSCs. The inspectors reviewed design documentation and plant procedures affected by the modifications to verify the licensee maintained configuration contro l. These activities constitute d completion of two sample s of temporary modifications, as defined in Inspection Procedure 71111.18.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R19}}
==1R19 Post-Maintenance==


Testing (71111.19)
1 R 19 Post-Maintenance Testing (71111.19)


====a. Inspection Scope====
====a. Inspection Scope====
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August 17, 2016, raw water pump AC-10 post-maintenance test September 8, 2016, replace battery charger 3 float potentiometer September 19, 2016, replace time delay agastat relay for component cooling water pump AC
August 17, 2016, raw water pump AC-10 post-maintenance test September 8, 2016, replace battery charger 3 float potentiometer September 19, 2016, replace time delay agastat relay for component cooling water pump AC
-3B from DC sequencer S 2-1 September 20, 2016, refurbishment of compressed air CA
-3B from DC sequencer S 2-1 September 20, 2016, refurbishment of compressed air CA
-1B air compressor September 26, 2016, removal of a failed Loop 2 Thot resistance temperature detector from the B reactor protecti ve system instrument channel The inspectors reviewed licensing- and design
-1B air compressor September 26, 2016, removal of a failed Loop 2 T hot resistance temperature detector from the B reactor protecti ve system instrument channel The inspectors reviewed licensing- and design
-basis documents for the SSCs and the maintenance and post-maintenance test procedures.
-basis documents for the SSCs and the maintenance and post-maintenance test procedures.


The inspectors observed the performance of the post
The inspectors observed the performance of the post
-maintenance tests to verify that the licensee performed the tests in accordance with approved procedures, satisfied the established acceptance criteria, and restored the operability of the affected SSCs
-maintenance tests to verify that the licensee performed the tests in accordance with approved procedures, satisfied the established acceptance criteria, and restored the operability of the affected SSCs
. These activities constitute d completion of five post-maintenance testing inspection samples, as defined in Inspection Procedure 71111.19.
. These activities constitute d completion of five post-maintenance testing inspection samples , as defined in Inspection Procedure 71111.19.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|1R22}}
 
==1R22 Surveillance Testing==
1 R 22 Surveillance Testing (71111.22)
{{IP sample|IP=IP 71111.22}}


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors observed nine risk-significant surveillance tests and reviewed test results to verify that these tests adequately demonstrated that the structures, systems, and components (SSCs) were capable of performing their safety functions:
The inspectors observed nine risk-significant surveillance tests and reviewed test results to verify that these tests adequately demonstrated that the structures, systems, and components (SSCs) were capable of performing their safety functions:
In-service tests:  August 19, 2016, component cooling water pump AC
In-service test s:  August 19, 2016, component cooling water pump AC
-3A in-service test September 9, 2016, safety injection/containment spray pumps in-service and valve exercise test  September 30, 2016, raw water pump AC
-3A in-service test September 9, 2016, safety injection/containment spray pumps in-service an d valve exercise test  September 30, 2016, raw water pump AC
-10D in-service test Containment isolation valve surveillance tests:  July 20, 2016, containment cooler inlet and outlet valves surveillance test Reactor coolant system leak detection tests:  September 28, 2016
-10D in-service test Containment isolation valve surveillance tests:  July 20, 2016, containment cooler inlet and outlet valves surveillance test Reactor coolant system leak detection tests:  September 28, 2016 , reactor coolant system leak detection test Other surveillance tests:
, reactor coolant system leak detection test Other surveillance tests:
July 15, 2016, emergency diesel generator 1 S1-2 automatic load sequencer surveillance test  August 4, 2016, chemical and volume control system boric acid pump CH
July 15, 2016, emergency diesel generator 1 S1-2 automatic load sequencer surveillance test  August 4, 2016, chemical and volume control system boric acid pump CH
-4B surveillance test August 19, 2016, ventilating air system Category A valve exercise surveillance test September 20, 2016, diesel driven auxillary feedwater pump FW-54 full flow operability verification test The inspectors verified that these test s met technical specification requirements, that the licensee performed the tests in accordance with their procedures, and that the results of the tests satisfied appropriate acceptance criteria. The inspectors verified that the licensee restored the operability of the affected SSCs following testing.
-4B surveillance test August 19, 2016, ventilating air system Category A valve exercise surveillance tes t September 20, 2016, diesel driven auxillary feedwater pump FW-54 full flow operability verification test The inspectors verified that these test s met technical specification requirements, that the licensee performed the tests in accordance with their procedures, and that the results of the test s satisfied appropriate acceptance criteria. The inspectors verified that the licensee restored the operability of the affected SSCs following testing.


These activities constitute d completion of nine surveillance testing inspection samples, as defined in Inspection Procedure 71111.22.
These activities constitute d completion of nine surveillance testing inspection samples , a s defined in Inspection Procedure 71111.22.


====b. Findings====
====b. Findings====
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===Cornerstone:===
===Cornerstone:===
Emergency Preparedness
Emergency Preparedness 1 EP 6 Drill Evaluation (71114.06)
{{a|1EP6}}
==1EP6 Drill Evaluation==
{{IP sample|IP=IP 71114.06}}
Emergency Preparedness Drill Observation
Emergency Preparedness Drill Observation


Line 345: Line 314:
-drill critique and entered into the corrective action program for resolution.
-drill critique and entered into the corrective action program for resolution.


These activities constitute d completion of one emergency preparedness drill observation sample, as defined in Inspection Procedure 71114.06.
These activities constitute d completion of one emergency preparedness drill observation sample, as defined in Inspection Procedure 71114.0 6.


====b. Findings====
====b. Findings====
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==RADIATION SAFETY==
==RADIATION SAFETY==
Cornerstones:
Cornerstones:
Public Radiation Safety and Occupational Radiation Safety
Public Radiation Safety and Occupational Radiation Safety 2 RS 1 Radiological Hazard Assessment and Exposure Controls (71124.01)
{{a|2RS1}}
==2RS1 Radiological Hazard Assessment and Exposure Controls==
{{IP sample|IP=IP 71124.01}}


====a. Inspection Scope====
====a. Inspection Scope====
Line 363: Line 329:
.
.


Instructions to workers including radiation work permit requirements and restrictions, actions for electronic dosimeter alarms, changing radiological condition, and radioactive material container labeling.
Instructions to workers including radiation work permit requirements and restrictions, actions for electronic dosimeter alarms , changing radiological condition, and radioactive material container labeling.


Contamination and radioactive material control
Contamination and radioactive material control
Line 383: Line 349:
====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|2RS5}}
 
==2RS5 Radiation Monitoring Instrumentation==
2 RS 5 Radiation Monitoring Instrumentation (71124.05)
{{IP sample|IP=IP 71124.05}}


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors evaluated the accuracy and operability of the radiation monitoring equipment used by the licensee to monitor areas, materials, and workers to ensure a radiologically safe work environment. This evaluation included equipment used to monitor radiological conditions related to normal plant operations, anticipated operational occurrences, and conditions resulting from postulated accidents
The inspectors evaluated the accuracy and operability of the radiation monitoring equipment used by the licensee to monitor areas, materials, and workers to ensure a radiologically safe work environment. This evaluation included equipment used to monitor radiological conditions related to normal plant operations, anticipated operational occurrences, and conditions resulting from postulated accidents. The inspectors interviewed licensee personnel, walked down various portions of the plant, and reviewed licensee performance associated with radiation monitoring instrumentation, as described below:    The inspectors performed walk
. The inspectors interviewed licensee personnel, walked down various portions of the plant, and reviewed licensee performance associated with radiation monitoring instrumentation, as described below:    The inspectors performed walk
-downs and observations of selected plant radiation monitoring equipment and instrumentation, including portable survey  
-downs and observations of selected plant radiation monitoring equipment and instrumentation, including portable survey  


Line 395: Line 359:
.
.


The inspectors evaluated the calibration and testing program, including laboratory instrumentation
The inspectors evaluated the calibration and testing program, including laboratory instrumentation , whole body counters , post-accident monitoring instrumentation, portal monitors, personnel contamination monitors, small article monitors , portable survey instruments, area radiation monitors , electronic dosimetry , air samplers, and continuous air monitors
, whole body counters
, post-accident monitoring instrumentation, portal monitors, personnel contamination monitors, small article monitors, portable survey instruments, area radiation monitors
, electronic dosimetry
, air samplers, and continuous air monitors
.
.


Line 415: Line 375:
====a. Inspection Scope====
====a. Inspection Scope====
The inspectors evaluated whether the licensee maintained gaseous and liquid effluent processing systems and properly mitigated, monitored, and evaluated radiological discharges with respect to public exposure. The inspectors verified that abnormal radioactive gaseous or liquid discharges and conditions, when effluent radiation monitors are out-of-service, were controlled in accordance with the applicable regulatory requirements and licensee procedures. The inspectors verified that the licensee's quality control program ensured radioactive effluent sampling and analysis adequately quantified and evaluated discharges of radioactive materials. The inspectors verified the adequacy of public dose projections resulting from radioactive effluent discharges. The inspectors interviewed licensee personnel and reviewed licensee performance in the following areas:
The inspectors evaluated whether the licensee maintained gaseous and liquid effluent processing systems and properly mitigated, monitored, and evaluated radiological discharges with respect to public exposure. The inspectors verified that abnormal radioactive gaseous or liquid discharges and conditions, when effluent radiation monitors are out-of-service, were controlled in accordance with the applicable regulatory requirements and licensee procedures. The inspectors verified that the licensee's quality control program ensured radioactive effluent sampling and analysis adequately quantified and evaluated discharges of radioactive materials. The inspectors verified the adequacy of public dose projections resulting from radioactive effluent discharges. The inspectors interviewed licensee personnel and reviewed licensee performance in the following areas:
During walk-downs and observations of selected portions of the radioactive gaseous and liquid effluent equipment, the inspectors evaluated routine processing and discharge of effluents, including sample collection and analysis
During walk-downs and observations of selected portions of the radioactive gaseous and liquid effluent equipment, the inspectors evaluated routine processing and discharge of effluents, including sample collection and analysis. The inspectors observed equipment configuration and flow paths of selected gaseous and liquid discharge system components , effluent monitoring systems, filtered ventilation system material condition, and significant changes to effluent release points.
. The inspectors observed equipment configuration and flow paths of selected gaseous and liquid discharge system components
, effluent monitoring systems, filtered ventilation system material condition, and significant changes to effluent release points.


Calibration and testing program for process and effluent monitors, including National Institute of Standards and Technology (NIST) traceability of sources
Calibration and testing program for process and effluent monitors, including National Institute of Standards and Technology (NIST) traceability of sources , primary and secondary calibration data, channel calibrations, set-point determination bases, and surveillance test results
, primary and secondary calibration data, channel calibrations, set-point determination bases, and surveillance test results
.
.


Line 431: Line 388:
Dose calculations for effluent releases. The inspectors reviewed a selection of radioactive liquid and gaseous waste discharge permits and abnormal gaseous or liquid tank discharges, and verified the projected doses were accurate. The inspectors also reviewed 10 CFR Part 61 analyses and methods used to determine which isotopes were included in the source term. The inspectors reviewed land use census results, offsite dose calculation manual changes, and significant changes in reported dose values from previous years.
Dose calculations for effluent releases. The inspectors reviewed a selection of radioactive liquid and gaseous waste discharge permits and abnormal gaseous or liquid tank discharges, and verified the projected doses were accurate. The inspectors also reviewed 10 CFR Part 61 analyses and methods used to determine which isotopes were included in the source term. The inspectors reviewed land use census results, offsite dose calculation manual changes, and significant changes in reported dose values from previous years.


Problem identification and resolution for radioactive gaseous and liquid effluent treatment. The inspectors reviewed audits, self
Problem identification and resolution for radioactive gaseous and liquid effluent treatment. The inspectors reviewed audits, self-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.
-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.


These activities constitute d completion of the six required samples of radioactive gaseous and liquid effluent treatment program, as defined in Inspection Procedure 71124.06.
These activities constitute d completion of the six required samples of radioactive gaseous and liquid effluent treatment program, as defined in Inspection Procedure 7112 4.0 6.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|2RS8}}
 
==2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation==
2 RS 8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation (71124.08)
{{IP sample|IP=IP 71124.08}}


====a. Inspection Scope====
====a. Inspection Scope====
Line 450: Line 405:
. Radioactive waste system
. Radioactive waste system
, including walk
, including walk
-downs of the accessible portions of the radioactive waste processing systems and handling equipment. The inspectors also reviewed or observed changes made to the radioactive waste processing systems, methods for dewatering and waste stabilization, waste stream mixing methodology, and waste processing equipment that was not operational or abandoned in place
-downs of the accessible portions of the radioactive waste processing systems and handling equipment. The inspectors also review ed or observed changes made to the radioactive waste processing systems, methods for dewatering and waste stabilization, waste stream mixing methodology, and waste processing equipment that was not operational or abandoned in place
. Waste characterization and classification
. Waste characterization and classification
, including radio-chemical sample analysis results for radioactive waste streams and use of scaling factors and calculations to account for difficult
, including radio-chemical sample analysis results for radioactive waste streams and use of scaling factors and calculations to account for difficult
-to-measure radionuclides, and processes for waste classification including use of scaling factors and 10 CFR Part 61 analyses. Shipment preparation, including packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and preparation of the disposal manifests. Shipping records for LSA I, II, III, SCO I, II, Type A, or Type B radioactive material or radioactive waste shipments.
-to-measure radionuclides, and processes for waste classification including use of scaling factors and 10 CFR Part 61 analyses. Shipment preparation, including packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and preparation of the disposal manifest s. Shipping records for LSA I, II, III, SCO I, II, Type A, or Type B radioactive material or radioactive waste shipments.


Problem identification and resolution for radioactive solid waste processing and radioactive material handling, storage, and transportation. The inspectors reviewed audits, self
Problem identification and resolution for radioactive solid waste processing and radioactive material handling, storage, and transportation. The inspectors reviewed audits, self
Line 466: Line 421:


==OTHER ACTIVITIES==
==OTHER ACTIVITIES==
Cornerstones:  Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness, Public Radiation Safety, Occupational Radiation Safety, and Security
Cornerstones:  Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness, Public Radiation Safety, Occupational Radiation Safety, and Security 4OA 1 Performance Indicator Verification (71151)
{{a|4OA1}}
 
==4OA1 Performance Indicator Verification==
{{IP sample|IP=IP 71151}}
===.1 Mitigating Systems Performance Index===
===.1 Mitigating Systems Performance Index===
: High Pressure Injection Systems (MS07)
: High Pressure Injection Systems (MS07)


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors reviewed the licensee's mitigating system performance index data for the period of July 1, 2015, through June 30, 2016, to verify the accuracy and completeness of the reported data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.
The inspectors reviewed the licensee's mitigating system performance index data for the period of July 1, 2015 , through June 30, 2016, to verify the accuracy and completeness of the reported data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.


These activities constituted verification of the mitigating system performance index for high pressure injection systems, as defined in Inspection Procedure 71151.
These activities constituted verification of the mitigating system performance index for high pressure injection systems, as defined in Inspection Procedure 71151.
Line 506: Line 459:


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors verified that there were no unplanned exposures or losses of radiological control over locked high radiation areas and very high radiation areas during the period of April 1, 2015, to June 30, 2016. The inspectors reviewed a sample of radiologically controlled area exit transactions showing exposures greater than 100 millirem. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.
The inspectors verified that there were no unplanned exposures or losses of radiological control over locked high radiation areas and very high radiation areas during the period of April 1, 2015, to June 30, 2016. The inspectors reviewed a sample of radiologically controlled area exit transactions showing exposures greater than 100 millirem. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7 , to determine the accuracy of the reported data.


These activities constituted verification of the occupational exposure control effectiveness performance indicator
These activities constituted verification of the occupational exposure control effectiveness performance indicator
Line 517: Line 470:


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors reviewed corrective action program records for liquid or gaseous effluent releases that occurred between April 1, 2015, and June 30, 2016, and were reported to the NRC to verify the performance indicator data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.
The inspectors reviewed corrective action program records for liquid or gaseous effluent releases that occurred between April 1, 2015 , and June 30, 2016, and were reported to the NRC to verify the performance indicator data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.


These activities constituted verification of the radiological effluent technical specifications (RETS)/offsite dose calculation manual (ODCM) radiological effluent occurrences performance indicator
These activities constituted verification of the radiological effluent technical specifications (RETS)/offsite dose calculation manual (ODCM) radiological effluent occurrences performance indicator
Line 525: Line 478:
No findings were identified.
No findings were identified.


{{a|4OA2}}
4OA 2 Problem Identification and Resolution (71152)
==4OA2 Problem Identification and Resolution==
 
(71152)


===.1 Routine Review===
===.1 Routine Review===


====a. Inspection Scope====
====a. Inspection Scope====
Throughout the inspection period, the inspectors performed daily reviews of items entered into the licensee's corrective action program and periodically attended the licensee's condition report screening meetings
Throughout the inspection period, the inspectors performed daily reviews of items entered into the licensee's corrective action program and periodically attended the licensee's condition report screening meetings. The inspectors verified that licensee personnel were identifying problems at an appropriate threshold and entering these problems into the corrective action program for resolution. The inspectors verified that the licensee developed and implemented corrective actions commensurate with the significance of the problems identified.
. The inspectors verified that licensee personnel were identifying problems at an appropriate threshold and entering these problems into the corrective action program for resolution. The inspectors verified that the licensee developed and implemented corrective actions commensurate with the significance of the problems identified.


The inspectors also reviewed the licensee's problem identification and resolution activities during the performance of the other inspection activities documented in this report.
The inspectors also reviewed the licensee's problem identification and resolution activities during the performance of the other inspection activities documented in this report.
Line 546: Line 495:


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors selected one issue for an in-depth follow-up:  On September 30, 2016
The inspectors selected one issue for an in-depth follow-up:  On September 30, 2016 , in leakage into safety injection tank 6A.
, in leakage into safety injection tank 6A.


The inspectors assessed the licensee's problem identification threshold, cause analyses, extent of condition reviews and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition.
The inspectors assessed the licensee's problem identification threshold, cause analyses, extent of condition reviews and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition.


These activities constitute d completion of one annual follow-up sample as defined i n Inspection Procedure 71152.
These activities constitute d completion of one annual follow-up sample a s defined i n Inspection Procedure 71152.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|4OA3}}
 
==4OA3 Follow-up of Events and Notices of Enforcement Discretion==
4OA 3 Follow-up of Events and Notices of Enforcement Discretion (71153)
{{IP sample|IP=IP 71153}}
 
===.1 Plant Events===
===.1 Plant Events===


Line 571: Line 519:
===.2 (Closed) Licensee Event Report 05000285/2016===
===.2 (Closed) Licensee Event Report 05000285/2016===


00, "Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor"
00 , "Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor"


====a. Inspection Scope====
====a. Inspection Scope====
On February 10, 2016, the licensee became aware of a 10 CFR 21.21 nonconformance notification issued by Canberra Industries, Incorporated. Canberra identified that some components from purchase orders associated with radiation monitors had not fully met 10 CFR 50.49 electrical equipment qualification standard s. It was determined that certain components (time delay, mass flow controller, and vacuum pump motor) in specific radiation monitors (RMs)
On February 1 0, 2016 , the licensee became aware of a 10 CFR 21.21 nonconformance notification issued by Canberra Industries, Incorporated. Canberra identified that some components from purchase orders associated with radiation monitors had not fully met 10 CFR 50.49 electrical equipment qualification standard s. It was determined that certain components (time delay, mass flow controller, and vacuum pump motor) in specific radiation monitors (RMs)
-50, -51, and -52 may not be qualified for the potential worst case environmental conditions during an electromagnetic, high temperature or seismic event. By February 12, 2016, the licensee and Canberra located the components that should have been included in the electrical equipment qualification program. Eventually, the licensee determined that only RM
-50, -51, and -52 may not be qualified for the potential worst case environmental conditions during an electromagnetic, high temperature or seismic event. By February 12, 2016, t he licensee and Canberra located the components that should have been included in the electrical equipment qualification program. Eventually, the licensee determined that only RM
-52 (auxiliary building vent stack monitor) had an unqualified part installed, a time delay relay.
-52 (auxiliary building vent stack monitor) had an unqualified part installed, a time delay relay.


Line 585: Line 533:
No findings were identified.
No findings were identified.


===.3 (Closed) Violation===
===.3 (Closed) Violation 05000285/2015010-01, "Failure to Provide Complete and Accurate Information on Licensed Operator Applications"===


05000285/
The NRC issued this cited violation of 10 CFR 50.9, "Completeness and Accuracy of Information," for the Fort Calhoun Station's failure to perform combustion odor testing as required in American National Standards Institute Standard 3.4-1996 for physical examinations of licensed operators and as documented in NRC Form 396, "Certification of Medical Examination by Facility Licensee."  To address this violation, the licensee initiated Condition Report C R 2014-05108. The inspectors reviewed the actions documented in Condition Report CR 2014-05108 and the subsequent condition reports. Those corrective actions included testing all licensed operators for combustion odor testing prior to taking their next scheduled watch, and revising Procedure OP
2015010-01, "Failure to Provide Complete and Accurate Information on Licensed Operator Applications" The NRC issued this cited violation of 10 CFR 50.9, "Completeness and Accuracy of Information," for the Fort Calhoun Station's failure to perform combustion odor testing as required in American National Standards Institute Standard 3.4-1996 for physical examinations of licensed operators and as documented in NRC Form 396, "Certification of Medical Examination by Facility Licensee."  To address this violation, the licensee initiated Condition Report C R 2014-05108. The inspectors reviewed the actions documented in Condition Report CR 2014-05108 and the subsequent condition reports. Those corrective actions included testing all licensed operators for combustion odor testing prior to taking their next scheduled watch, and revising Procedure OP
-AA-105-101, "Administrative Process for NRC License and Medical Requirements," to bring the Exelon fleet model to Fort Calhoun Station. The inspectors determined that through these actions, the licensee restored compliance to 10 CFR 55.23. This violation is closed.
-AA-105-101, "Administrative Process for NRC License and Medical Requirements," to bring the Exelon fleet model to Fort Calhoun Station. The inspectors determined that through these actions, the licensee restored compliance to 10 CFR 55.23. This violation is closed.


Line 609: Line 556:
====b. Observations and Findings====
====b. Observations and Findings====
The licensee determined the cause was leadership had not provided adequate governance and oversight to influence behaviors and hold personnel accountable. The licensee also determined that the traditional enforcement issues were driven by human performance errors and were primarily associated with the implementation of the 10 CFR 50.59 process by engineering personnel. The licensee reviewed traditional enforcement violations from the previous 12
The licensee determined the cause was leadership had not provided adequate governance and oversight to influence behaviors and hold personnel accountable. The licensee also determined that the traditional enforcement issues were driven by human performance errors and were primarily associated with the implementation of the 10 CFR 50.59 process by engineering personnel. The licensee reviewed traditional enforcement violations from the previous 12
-month time period and identified similar issues and drivers (e.g.,
-month time period and identified similar issues and drivers (e.g., several 10 CFR 50.59 process implementation issues). The inspectors determined the SLIV violations received an evaluation at an appropriate level of detail to identify the causes and included review of prior occurrences. The inspectors also conclude d the evaluation of the traditional enforcement violations included an appropriate extent of condition and extent of cause of the issues.
several 10 CFR 50.59 process implementation issues). The inspectors determined the SLIV violations received an evaluation at an appropriate level of detail to identify the causes and included review of prior occurrences. The inspectors also conclude d the evaluation of the traditional enforcement violations included an appropriate extent of condition and extent of cause of the issues.
 
The licensee credited several high level corrective actions previously implemented during their recovery while in the Inspection Manual Chapter 0350 process. These actions included; development of governance and oversight policies and transition to the Exelon Management model, implementation of a new engineering organizational structure, development and implementation of an Institute of Nuclear Power Operations (INPO) Human Performance Strategic Plan, and the development of an interim Engineering Assurance Group to review engineering product quality. In addition, actions were taken specifically to improve engineering performance and 10 CFR 50.59 process implementation. The actions included 10 CFR 50.59 training, limiting the number of personnel qualified to perform 10 CFR 50.59 evaluations and reviews
, and the development of key performance indicators to trend the quality of these engineering products.


The inspectors determined these corrective actions were comprehensive and appropriate to improve overall site performance and specifically to improve 10 CFR 50.59 process and engineering department performance. The inspectors also determined that the corrective actions were prioritized and implemented on a schedule reflective of the organizational turn around necessary to improve site performance. The inspectors noted that although some actions had not appeared to have been in place long enough to effectively preclude the traditional enforcement violations that were identified in the 2014 to 2015 time period, overall site and specifically engineering performance has improved since this time
The licensee credited several high level corrective actions previously implemented during their recovery while in the Inspection Manual Chapter 0350 process. These actions included; development of governance and oversight policies and transition to t he Exelon Management model, implementation of a new engineering organizational structure, development and implementation of an Institute of Nuclear Power Operations (INPO) Human Performance Strategic Plan, and the development of an interim Engineering Assurance Group to review engineering product quality. In addition, actions were taken specifically to improve engineering performance and 10 CFR 50.59 process implementation. The actions included 10 CFR 50.59 training, limiting the number of personnel qualified to perform 10 CFR 50.59 evaluations and reviews
, and the development of key performance indicators to trend the quality of these engineering products. The inspectors determined these corrective actions were comprehensive and appropriate to improve overall site performance and specifically to improve 10 CFR 50.59 process and engineering department performance. The inspectors also determined that the corrective actions were prioritized and implemented on a schedule reflective of the organizational turn around necessary to improve site performance. The inspectors noted that although some actions had not appeared to have been in place long enough to effectively preclude the traditional enforcement violations that were identified in the 2014 to 2015 time period, overall site and specifically engineering performance has improved since this time
.
.
The licensee identified several success measures to determine the effectiveness of the traditional enforcement corrective actions including:  verification of the completion of engineering training classes, a Nuclear Oversight department audit of the design process (including the 10 CFR 50.59 process with no findings), a successful check
The licensee identified several success measures to determine the effectiveness of the traditional enforcement corrective actions including:  verification of the completion of engineering training classes, a Nuclear Oversight department audit of the design process (including the 10 CFR 50.59 process with no findings), a successful check
Line 623: Line 567:
No findings were identified.
No findings were identified.


{{a|4OA6}}
4OA 6 Meetings, Including Exit
==4OA6 Meetings, Including Exit==


===Exit Meeting Summary===
===Exit Meeting Summary===
Line 632: Line 575:
On September 28, 2016, the inspectors briefed Mr. S. Marik, Vice President and Chief Nuclear Officer, and other members of the licensee's staff of the results of the licensed operator requalification program inspection. The licensee representatives acknowledged the findings presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
On September 28, 2016, the inspectors briefed Mr. S. Marik, Vice President and Chief Nuclear Officer, and other members of the licensee's staff of the results of the licensed operator requalification program inspection. The licensee representatives acknowledged the findings presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.


On October 12, 2016, the inspectors presented the inspection results to Mr. M. Prospero
On October 12, 2016, the inspectors presented the inspection results to Mr. M. Prospero , Acting Site Vice President, and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.
, Acting Site Vice President, and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=
Line 810: Line 752:
: 2016
: 2016
: Post Event Simulator Tes
: Post Event Simulator Tes
t December 17, 2014
t December 17, 20 14
: Post Event Simulator Test March 17,  
: Post Event Simulator Test March 17, 20 14
: 2014
: Post Event Simulator Test July 27, 20
: Post Event Simulator Test July 27, 20
: Simulator Work Requests  
: Simulator Work Requests  
- open and closed from last two years 2015-2016 2.6 Technical Specification, Containment System
- open and closed from last two years 2015-2016 2.6 Technical Specification, Containment System
: CFR 55.46
: CFR 55.46
: Simulator Facilities January 1,  
: Simulator Facilities January 1, 2016 161F561 SPEC 200 Loop Diagram:
: 2016 161F561 SPEC 200 Loop Diagram:
: Loop B/TE
: Loop B/TE
-112C, B/TE
-112C, B/TE
Line 844: Line 784:
-4 Power
-4 Power
: AI-41A 48
: AI-41A 48
: HR-AA-07-101 NRC Licensed Operator Medical Examination
: HR-AA-07-101 N RC Licensed Operator Medical Examination
: OI-FW-5 Steam Generator Blowdown Normal Operation
: OI-FW-5 Steam Generator Blowdown Normal Operation
: OP-AA-101-113 Operator Fundamentals
: OP-AA-101-113 Operator Fundamentals
Line 861: Line 801:
: TQ-AA-201 Examination Security and Administration
: TQ-AA-201 Examination Security and Administration
: TQ-AA-223 Required Reading Training Package  
: TQ-AA-223 Required Reading Training Package  
- Deboration and Coastdown Overview August 29,  
- Deboration and Coastdown Overview August 29, 20 16
: 2016
: TQ-FC-201-J01, App A Licensed Operator Training Simulator Checklist (FCS Specific) 1
: TQ-FC-201-J01, App A Licensed Operator Training Simulator Checklist (FCS Specific)
: TQ-FC-306 Simulator Management
: TQ-FC-306 Simulator Management
: TQ-FC-SS-50 Simulator Steady State Test  
: TQ-FC-SS-50 Simulator Steady State Test  
Line 924: Line 863:
: Title Revision/Date
: Title Revision/Date
: Adverse Condition Monitoring Plan, RC
: Adverse Condition Monitoring Plan, RC
-3A Reactor Coolant Pump Motor Lower Oil Reservoir Level Indication August 15,  
-3A Reactor Coolant Pump Motor Lower Oil Reservoir Level Indication August 15, 2016
: 2016
: Event Notification for an Unanalyzed Condition that Significantly Degrades Plant Safety and a Condition that could have Prevented Fulfillment of a Safety Function August 25, 2016
: Event Notification for an Unanalyzed Condition that Significantly Degrades Plant Safety and a Condition that could have Prevented Fulfillment of a Safety Function August 25,  
: 2016
: Fort Calhoun Site Risk Issue Summary Report September 28, 2016
: Fort Calhoun Site Risk Issue Summary Report September 28, 2016
: Fort Calhoun Site Risk Map September 28, 2016
: Fort Calhoun Site Risk Map September 28, 2016
Line 980: Line 917:
: 50.59 Review for
: 50.59 Review for
: EC 68783/Op Eval 16
: EC 68783/Op Eval 16
-002 August 8,  
-002 August 8, 2016 50.59 Screening Form for EC 68783
: 2016 50.59 Screening Form for EC 68783
: August 8, 2016 60183 Engineering Change, Tornado Protection for Pull Boxes
: August 8,  
: 2016 60183 Engineering Change, Tornado Protection for Pull Boxes
: PB-128T and
: PB-128T and
: PB-129T 3  
: PB-129T 3  
Line 998: Line 933:
: PB-129T 3
: PB-129T 3
: SK-EC60183-01 Drawing, Tornado Missile Barrier for Pull Boxes PB
: SK-EC60183-01 Drawing, Tornado Missile Barrier for Pull Boxes PB
-128T and
-12 8 T and
: PB-129T E  
: PB-129T E  
===Procedures===
===Procedures===
Line 1,021: Line 956:
===Miscellaneous Documents===
===Miscellaneous Documents===
: Number Title Revision
: Number Title Revision
: Electrical Troubleshooting Log August 31,  
: Electrical Troubleshooting Log August 31, 2016  
: 2016  
===Miscellaneous Documents===
===Miscellaneous Documents===
: Number Title Revision
: Number Title Revision
: Diesel Generator Sequence
: Diesel Generator Sequence
r Report September 1,  
r Report September 1, 2016
: 2016
: Maintenance Alterations Log for WO 00592537
: Maintenance Alterations Log for WO 00592537
-02 September 1,  
-02 September 1, 2016 161F598 Drawing, AI
: 2016 161F598 Drawing, AI
-30B DC Sequencer S2
-30B DC Sequencer S2
-1 Auto Start Circuit 480V Bus 1B4C and Bus Tie 1B3C
-1 Auto Start Circuit 480V Bus 1B4C and Bus Tie 1B3C
Line 1,076: Line 1,008:
: 00591969 Task 01, EE
: 00591969 Task 01, EE
-8E; Replace CFA Board and DSL Board for Battery Charger #3
-8E; Replace CFA Board and DSL Board for Battery Charger #3
: 00592537 Task 02, Replace Time Delay Pick Up Relay on Sequencer
: 00592537 Task 02, Replace Time Delay Pick Up Relay on Sequencer S2-1 for
: S2-1 for
: AC-3B
: AC-3B
: 00593556 Task 02, B/TI-122H; Perform Troubleshooting per
: 00593556 Task 02, B/TI-122H; Perform Troubleshooting per
Line 1,097: Line 1,028:
: Updated Safety Analysis Report (USAR), Chapter 8.4, Emergency Power Sources Updated Safety Analysis Report (USAR), Chapter 7.3, Engineered Safeguards Controls and Instrumentation
: Updated Safety Analysis Report (USAR), Chapter 8.4, Emergency Power Sources Updated Safety Analysis Report (USAR), Chapter 7.3, Engineered Safeguards Controls and Instrumentation
: 2.2 Technical Specification, Chemical and Volume Control System 249 Amendment 165
: 2.2 Technical Specification, Chemical and Volume Control System 249 Amendment 165
: NRC Safety Evaluation August 25,  
: NRC Safety Evaluation August 25, 1994 Chapter 9.2
: 1994 Chapter 9.2
: Updated Safety Analysis Report (USAR), Chemical and Volume Control System
: Updated Safety Analysis Report (USAR), Chemical and Volume Control System
: FC05462 Response Time of Containment Air Monitoring System  
: FC05462 Response Time of Containment Air Monitoring System  
Line 1,216: Line 1,146:
: NOSA-FCS-15-06 Radiation Protection Audit Report July 24, 2015
: NOSA-FCS-15-06 Radiation Protection Audit Report July 24, 2015
: P3 2015(2)
: P3 2015(2)
: FCS RMS System Health September 16,  
: FCS RMS System Health September 16, 2015 P4 2015(2) FCS RMS System Health June 26, 2016
: 2015 P4 2015(2
) FCS RMS System Health June 26, 2016
: P3 2016(2) FCS RMS System Health May 17, 2016
: P3 2016(2) FCS RMS System Health May 17, 2016
: Audits and Self
: Audits and Self
Line 1,229: Line 1,157:
: Number Title Date
: Number Title Date
: BX-3 Hopewell Calibration Irradiator Box February 19, 2015
: BX-3 Hopewell Calibration Irradiator Box February 19, 2015
: FC-15-001 Evaluation of Instrument Response to Plant Radiological Mix January 24, 2016
: FC-15-001 Evaluation of Instrument Response to Plant Radiol ogical Mix January 24, 2016
: FC-14-002 Evaluation of Instrument Response to Plant Radiological Mix May 28, 2014
: FC-14-002 Evaluation of Instrument Response to Plant Radiol ogical Mix May 28, 201 4
: Portable Radiation Instrument Calibration Records Number Title Date 279
: Portable Radiation Instrument Calibration Records Number Title Date 279
: ASP-2E (Remball)
: ASP-2E (Remball)
Line 1,238: Line 1,166:
: AMS-4 Continuous Air Monitor February 20, 2015
: AMS-4 Continuous Air Monitor February 20, 2015
: 691 Hi-Vol Air Sampler March 9, 2015
: 691 Hi-Vol Air Sampler March 9, 2015
: 291 Hi-Vol Air Sampler September 23, 2014 2554
: 291 Hi-Vol Air Sampler September 23, 201 4 2554
: AMS-4 Continuous Air Monitor March 7, 2015 2554
: AMS-4 Continuous Air Monitor March 7, 2015 2554
: AMS-4 Continuous Air Monitor June 6, 2015
: AMS-4 Continuous Air Monitor June 6, 2015
Line 1,245: Line 1,173:
===Procedures===
===Procedures===
: Number Title Revision
: Number Title Revision
: CH-CP-RA-0006 Calibration of Canberra Gamma Spectroscopy Detectors
: CH-CP-RA-0006 Calibration of Canberra Gamma Spectroscopy Detectors 13
: CH-CP-RM-5300 Component Cooling Water Liquid Radiation Monitor, RM
: CH-CP-RM-5300 Component Cooling Water Liquid Radiation Monitor, RM
-53, Primary Calibration
-53, Primary Calibration
Line 1,282: Line 1,210:
: RP-AA-700-1239 Operation & Calibration of the Model SAM 12
: RP-AA-700-1239 Operation & Calibration of the Model SAM 12
: TBD-IV.8 Area Monitoring Setpoints
: TBD-IV.8 Area Monitoring Setpoints
: TBD-IV.7 Process Monitor Setpoints
: TBD-IV.7 Process Monitor Setpoints 229
: 29
: Radiation Monitoring System Calibration Records Number Title Date
: Radiation Monitoring System Calibration Records Number Title Date
: WO-446910 Process Radiation Monitor RM
: WO-446910 Process Radiation Monitor RM
Line 1,300: Line 1,227:
-65 July 15, 2016
-65 July 15, 2016
: Stationary Radiation Instrument Calibration Records Number Title Date 110 Argos 5B January 6, 2016
: Stationary Radiation Instrument Calibration Records Number Title Date 110 Argos 5B January 6, 2016
: 111 Argos 5B December 10,  
: 111 Argos 5B December 10, 2015 133 Count Room SAM
: 2015 133 Count Room SAM
-12 December 2, 2015 134 Count Room SAM
-12 December 2, 2015 134 Count Room SAM
-12 August 27, 2015
-12 August 27, 2015
Line 1,312: Line 1,238:
: 2792 Ludlum Model 3030 Alpha
: 2792 Ludlum Model 3030 Alpha
-Beta Counter March 8, 2016
-Beta Counter March 8, 2016
: Admin FS2
: Admin FS2 Calibration Admin Bldg. FastScan2
: Calibration Admin Bldg. FastScan2
: WBC System November 3, 2015
: WBC System November 3, 2015
: Detector 1
: Detector 1
: Calibration of Canberra Gamma Spectroscopy Detectors December 15
: Calibration of Canberra Gamma Spectroscopy Detectors December 15 , 2015 Plant AC2 Calibration AccuScan2 WBC System February 25, 2016
, 2015 Plant AC2
: Plant FS 2 Calibration Admin Bldg.
: Calibration AccuScan2 WBC System February 25, 2016
: Plant FS2 Calibration Admin Bldg.
: FastScan2
: FastScan2
: WBC System February 25, 2016  
: WBC System February 25, 2016  
Line 1,343: Line 1,266:
: Steam Generator "B" Blowdown Liquid Radiation Monitor, RM
: Steam Generator "B" Blowdown Liquid Radiation Monitor, RM
-054B, Primary Calibration January 22, 2016
-054B, Primary Calibration January 22, 2016
: 000534700
: 000534700 Calibration of Auxiliary Building Exhaust Stack Total Ventilation Flow, Loop  
: Calibration of Auxiliary Building Exhaust Stack Total Ventilation Flow, Loop  
: F-758 April 28, 2016
: F-758 April 28, 2016
: 00485608 Electronic and Secondary Calibration of Radiation Monitor RM
: 00485608 Electronic and Secondary Calibration of Radiation Monitor RM
Line 1,381: Line 1,303:
-5A/VA-5B Refueling Inspection May 23, 2015
-5A/VA-5B Refueling Inspection May 23, 2015
: 00525582 Freon Test of Safety Injection Pump Room Charcoal Filter Absorbers
: 00525582 Freon Test of Safety Injection Pump Room Charcoal Filter Absorbers
: VA-26A/26B November 23,  
: VA-26A/26B November 23, 2015
: 2015
: 00540507 Freon Test of Spent Fuel Pool Area Charcoal Filter VA
: 00540507 Freon Test of Spent Fuel Pool Area Charcoal Filter VA
-66 October 26, 2015
-66 October 26, 2015
: 00543969 Safety Injection Pump Room Charcoal Filter VA
: 00543969 Safety Injection Pump Room Charcoal Filter VA
-26A/26B Elemental Iodine Removal Efficiency Test November 24,  
-26A/26B Elemental Iodine Removal Efficiency Test November 24, 2015   
: 2015   
: In-Place Filter Testing and Carbon Testing Records
: In-Place Filter Testing and Carbon Testing Records
: W/O Number Title Date
: W/O Number Title Date
Line 1,393: Line 1,313:
-66 Flow December 4, 2015  
-66 Flow December 4, 2015  
===Miscellaneous Documents===
===Miscellaneous Documents===
: Number Title Date 1st
: Number Title Date 1 st
: QTR 2016 Radiation Monitoring System Health Report
: QTR 2016 Radiation Monitoring System Health Report
: 2014 Annual Radiological Effluent Release Report
: 2014 Annual Radiological Effluent Release Report
Line 1,399: Line 1,319:
: 2015 Annual Radiological Effluent Release Report May 1, 2016
: 2015 Annual Radiological Effluent Release Report May 1, 2016
: 2015 Interlaboratory Comparison
: 2015 Interlaboratory Comparison
: 2006 Engineering Change: Replacement of Radiation Monitor Components December 22,  
: 2006 Engineering Change: Replacement of Radiation Monitor Components December 22, 2015 TD V964.0010
: 2015 TD V964.0010
: Installation, Operating and Maintenance Manual for Vortek Electronic Airflow Transmitter November 16, 1995  
: Installation, Operating and Maintenance Manual for Vortek Electronic Airflow Transmitter November 16, 1995  
===Procedures===
===Procedures===
Line 1,488: Line 1,407:
: Number Title Date
: Number Title Date
: FC-RP-037-14 2013 Dry Active Waste Stream Off
: FC-RP-037-14 2013 Dry Active Waste Stream Off
-Site Sample Results April 8,  
-Site Sample Results April 8, 2014  
: 2014  
===Procedures===
===Procedures===
: Number Title Revision/Date
: Number Title Revision/Date
Line 1,501: Line 1,419:
: RP-AA-600-1004 Radioactive Waste Shipments to Energy Solutions' Clive Utah Disposal Site Containerized Waste Facility
: RP-AA-600-1004 Radioactive Waste Shipments to Energy Solutions' Clive Utah Disposal Site Containerized Waste Facility
: RP-AA-600-1005 Radioactive Material and Non
: RP-AA-600-1005 Radioactive Material and Non
-Disposal Site Waste Shipments
-Disposal Site Waste Shipments 18
: RP-AA-600-1008 Radioactive Waste Shipments to Waste Control Specialists Disposal Facility
: RP-AA-600-1008 Radioactive Waste Shipments to Waste Control Specialists Disposal Facility
: RP-AA-600-1010 Use and Operation of WMG Software for Creating Containers, Samples, Waste Streams and Waste Types 2
: RP-AA-600-1010 Use and Operation of WMG Software for Creating Containers, Samples, Waste Streams and Waste Types 2
: RP-AA-601 Surveying Radioactive Material Shipments
: RP-AA-601 Surveying Radioactive Material Shipments
: RP-AA-602 Packaging of Radioactive Material Shipments
: RP-AA-602 Packaging of Radioactive Material Shipments
: RP-AA-603 Inspection and Loading of Radioactive Material Shipments
: RP-AA-603 Inspection and Loading of Radioactive Material Shipments 10
: RP-AA-605 10
: RP-AA-605 10
: CFR 61 Program
: CFR 61 Program
Line 1,517: Line 1,435:
: RW-AA-102 Radwaste Storage Facility/DAW Waste Container Inspections
: RW-AA-102 Radwaste Storage Facility/DAW Waste Container Inspections
: RW-AA-1000 Radwaste Monthly Report Guideline
: RW-AA-1000 Radwaste Monthly Report Guideline
: RW-AA-104 Radwaste Storage Facility/Waste Container Inspections Radioactive Materials Shipments Number Title Date 09-14 UN3321, Fissile
: RW-AA-104 Radwaste Storage Facility/Waste Container Inspections Radioactive Materials Shipments Number Title Date 09-14
-Excepted, Radioactive Material,
: UN 3321, Fissile-Excepted, Radioactive Material,
: LSA-II - Resin June 17, 2009
: LSA-II - Resin June 17, 2009
: 14-16 UN2910, Fissile
: 14-16 UN2910, Fissile
-Excepted, Radioactive Material, Limited Quantity November 13,  
-Excepted, Radioactive Material, Limited Quantity November 13, 2014 15-12 UN2912, Fissile-Excepted, Radioactive Material, LSA
: 2014 15-12 UN2912, Fissile-Excepted, Radioactive Material, LSA
-I - DAW April 21, 2015
-I - DAW April 21, 2015
: 15-15 UN2912, Fissile
: 15-15 UN2912, Fissile
Line 1,550: Line 1,467:
: Number Title Revision
: Number Title Revision
: LS-AA-2001 Collecting and Reporting of NRC Performance Indicator Data 14
: LS-AA-2001 Collecting and Reporting of NRC Performance Indicator Data 14
: LS-AA-2200 Mitigating System Performance Index Data Acquisition and Reporting  
: LS-AA-2200 Mitigating System Performance Index Data Acquisition and Reporting 5
===Condition Reports===
===Condition Reports===
(CRs)
(CRs)
Line 1,579: Line 1,496:
: AOP-12 Loss of Containment Integrity
: AOP-12 Loss of Containment Integrity
: EP-FC-1001 Emergency Action Levels for Fort Calhoun Station, Addendum 3
: EP-FC-1001 Emergency Action Levels for Fort Calhoun Station, Addendum 3
: EP-FC-1001 Radiological Emergency Response Plan for Fort Calhoun Station 0  
: EP-FC-1001 Radiological Emerg enc y Response Plan for Fort Calhoun Station 0  
===Condition Reports===
===Condition Reports===
(CRs)
(CRs)
Line 1,591: Line 1,508:
-Assessment of Design and Licensing Basis Configuration Control (CR  
-Assessment of Design and Licensing Basis Configuration Control (CR  
: 2013-05570-064) June 1, 2016
: 2013-05570-064) June 1, 2016
: Nuclear Oversight Audit Report, Engineering Design Control August 26,  
: Nuclear Oversight Audit Report, Engineering Design Control August 26, 2015
: 2015
: NED-13-155 DEN Site Vice President Memo, Restriction of Individuals Preparing/Reviewing 10
: NED-13-155 DEN Site Vice President Memo, Restriction of Individuals Preparing/Reviewing 10
: CFR 50.59 Product May 7, 2013
: CFR 50.59 Product May 7, 2013
Line 1,677: Line 1,593:
: 1. Calibration, use and operation of continuous air monitors, criticality monitors, portable survey instruments, temporary area radiation monitors, electronic dosimeters, teledosimetry, personnel contamination monitors, and whole body counters
: 1. Calibration, use and operation of continuous air monitors, criticality monitors, portable survey instruments, temporary area radiation monitors, electronic dosimeters, teledosimetry, personnel contamination monitors, and whole body counters
: 2. Calibration of installed radiation monitors
: 2. Calibration of installed radiation monitors
: E. Please provide specific procedures related to the following areas noted below
: E. Please provide specific procedures related to the following areas noted below.
.
: Additional Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
: Additional Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
: 1. Calibration of portable radiation detection instruments (for portable ion chambers)
: 1. Calibration of portable radiation detection instruments (for portable ion chambers)
Line 1,722: Line 1,637:
: 3. Generating radioactive effluent release permits
: 3. Generating radioactive effluent release permits
: 4. Laboratory instrumentation quality control
: 4. Laboratory instrumentation quality control
: 5. In-place testing of HEPA filters and charcoal absorbers
: 5. In-place testing of HEPA filters and charcoal absorbers
: 6. New or applicable procedures for effluent programs (e.g., including ground water monitoring programs)
: 6. New or applicable procedures for effluent programs (e.g., including ground water monitoring programs)
: F. List of corrective action documents (including corporate and sub
: F. List of corrective action documents (including corporate and sub
Line 1,787: Line 1,702:
: G. Copies of training lesson plans for 49CFR172 subpart H, for radwaste processing, packaging, and shipping
: G. Copies of training lesson plans for 49CFR172 subpart H, for radwaste processing, packaging, and shipping
: H. A summary of radioactive material and radioactive waste shipments made from date of last inspection to present
: H. A summary of radioactive material and radioactive waste shipments made from date of last inspection to present
: I. Waste stream sample analyses results and resulting scaling factors for 2014 and 2015
: I. Waste stream sample analyses results and resulting scaling factors for 2014 and 2015 , or the two most recent results
, or the two most recent results
: J. Waste classification reports if performed by vendors (such as for irradiated hardware)
: J. Waste classification reports if performed by vendors (such as for irradiated hardware)
: K. A listing of all onsite radwaste storage facilities.
: K. A listing of all onsite radwaste storage facilities.

Revision as of 03:30, 8 July 2018

Fort Calhoun Station - NRC Integrated Inspection Report Number 05000285/2016003
ML16315A180
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 11/08/2016
From: Miller G B
NRC/RGN-IV/DRP/RPB-D
To: Marik S M
Omaha Public Power District
GEOFF MILLER
References
IR 2016003
Download: ML16315A180 (66)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD.

ARLINGTON, TX 76011-4511 November 8, 2016 Shane M. Marik, Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station

Mail Stop FC

-2-4 9610 Power Lane Blair, NE 68008

SUBJECT: FORT CALHOUN STATION

- NRC INTEGRATED INSPECTION REPORT NUMBER 05000285/2016003

Dear Mr. Marik:

O n September 30, 201 6 , the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Fort Calhoun Station.

O n October 12, 2016, the NRC inspectors discussed the results of this inspection with Michael J. Prospero, Acting 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 findings or violations 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/ Geoffrey B. Miller, Branch Chief Project Branch D Division of Reactor Projects Docket No.

50-285 License No. DPR-40

Enclosure:

Inspection Report 05000285/2016003 w/

Attachment:

1. Supplemental Information 2. Request for Information for the Occupational/Public Radiation Safety Inspection

SUNSI Review By: GMiller ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: NRC-002 OFFICE SRI:DRP/D RI:DRP/D C:DRS/EB1 C:DRS/EB2 C:DRS/OB C:DRS/PSB2 TL:IPAT NAME MSchneider LBrandt TFarnholtz GWerner VGaddy HGepford THipschman SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 10/14/16 10/18/16 10/14/16 10/14/16 10/18/16 10/18/16 10/25/16 OFFICE BC:DRP/D NAME GMiller SIGNATURE /RA/ DATE 11/9/16 Letter to Shane from Geoffrey B. Miller dated November 8, 2016

SUBJECT: FORT CALHOUN STATION

- NRC INTEGRATED INSPECTION REPORT NUMBER 05000285/2016003 DISTRIBUTION

Regional Administrator (Kriss.Kennedy@nrc.gov) Deputy Regional Administrator (Scott.Morris@nrc.gov) DRP Director (Troy.Pruett@nrc.gov)

DRP Deputy Director (Ryan.Lantz@nrc.gov

) DRS Director (Anton.Vegel@nrc.gov)

DRS Deputy Director (Jeff.Clark@nrc.gov)

Senior Resident Inspector (Max.Schneider@nrc.gov)

Acting Resident Inspector (Shawn.Money@nrc.gov

) Acting Resident Inspector (Thomas.Sullivan@nrc.gov)

Acting Resident Inspector (Lindsay.Brandt@nrc.gov) Acting Site Administrative Assistant (Amy.Elam@nrc.gov) Branch Chief, DRP/D (Geoffrey.Miller@nrc.gov) Senior Project Engineer, DRP/E (John.Dixon@nrc.gov)

Project Engineer, DRP/D (Jim.Melfi@nrc.gov

) Project Engineer, DRP/D (Brian.Parks@nrc.gov)

Project Engineer, DRP/D (Jan.Tice@nrc.gov)

RIV Public Affairs Officer (Victor.Dricks@nrc.gov)

Project Manager (Fred.Lyon@nrc.gov)

Team Leader, DRS/IPAT (Thomas.Hipschman@nrc.gov

) Project Engineer, DRS/IPAT (Eduardo.Uribe@nrc.gov)

RIV RITS Coordinator (Marisa.Herrera@nrc.gov)

RIV Regional Counsel (Karla.Fuller@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov)

RIV/ETA: OEDO (Jeremy.Bowen@nrc.gov)

RIV RSLO (Bill.Maier@nrc.gov)

ACES (R4Enforcement.Resource@nrc.gov)

ROPreports.Resource@nrc.gov ROPassessment.Resource@nrc.gov Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000285 License: DPR-40 Report: 05000285/201600 3 Licensee: Omaha Public Power District Facility: Fort Calhoun Station Location: 9610 Power Lane Blair, NE 68008 Dates: July 1 through September 30, 2016 Inspectors:

S. Schneider, Senior Resident Inspector S. Money, Acting Resident Inspector T. Sullivan, Acting Resident Inspector L. Brandt, Acting Resident Inspector L. Carson II, Sr. Health Physicist N. Greene, PhD, Health Physicist P. Hernandez, Health Physicist J. Kirkland, Senior Operations Engineer J. O'Donnell, CHP, Health Physicist C. Cowdrey, Operations Engineer Approved By: Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects

SUMMARY

IR 05000285/2016003

0 7/01/2016 - 0 9/30/2016; Fort Calhoun Station
Integrated Inspection Report. The inspection activities described in this report were performed between July 1 and September 30 , 2016 , by the resident inspectors at Fort Calhoun Station and inspectors from the NRC's Region IV office. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process."

No findings were identified.

PLANT STATUS

The unit began the inspection period at approximately 98 percent power following start

-up from an unplanned automatic reactor trip and returned to 100 percent power on July 1, 2016. On September 29 , 2016, the licensee commenced a power coastdown

, and Fort Calhoun operated at approximately 98.5 percent power at the end of the inspection period.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, an d Barrier Integrity 1 R 01 Adverse Weather Protection (71111.01)

Readiness for Impending Adverse Weather Conditions

a. Inspection Scope

On September 6, 2016, the inspectors completed an inspection of the station's readiness for impending adverse weather conditions. The inspectors reviewed plant design features

, the licensee's procedures to respond to impending storms, and the licensee's compensatory actions to protect safety

-related equipment

. The inspectors evaluated operator staffing and accessibility of controls and indications for those systems required to control the plant and conducted a plant walk

-down. These activities constitute d one sample of readiness for impending adverse weather condition s , as defined in Inspection Procedure 71111.01.

b. Findings

No findings were identified.

1 R 04 Equipment Alignment (71111.04)

.1 Partial Walk

-Down

a. Inspection Scope

The inspectors performed partial system walk

-downs of the following risk-significant systems: July 13, 2016, emergency diesel generator 2 during testing on emergency diesel generator 1 July 18, 2016, steam driven auxiliary feedwater pump FW-10 prior to motor driven auxiliary feedwater pump FW-6 operability test September 20, 2016, auxiliary feedwater system prior to steam driven auxillary feedwater pump FW-10 operability test September 26, 2016, component cooling water system with component cooling water pump AC-3 B out of service for maintenance The inspectors reviewed the licensee's procedures and system design information to determine the correct lineup for the systems. They visually verified that critical portions of the systems were correctly aligned for the existing plant configuration

. These activities constitute d four partial system walk

-down samples a s defined i n Inspection Procedure 71111.04.

b. Findings

No findings were identified.

.2 Complete Walk

-Down

a. Inspection Scope

On August 19, 2016, the inspectors performed a complete system walk-down inspection of the spent fuel pool cooling system. The inspectors reviewed the licensee's procedures and system design information to determine the correct system lineup for the existing plant configuration. The inspectors also reviewed open condition reports, in-process design changes, and other open items tracked by the licensee's operations and engineering departments.

The inspectors then visually verified that the system was correctly aligned for the existing plant configuration.

These activities constitute d o ne complete system walk

-down sample , as defined in Inspection Procedure 71111.04.

b. Findings

No findings were identified.

1 R 05 Fire Protection (71111.05)

Quarterly Inspection

a. Inspection Scope

The inspectors evaluated the licensee's fire protection program for operational status and material condition. The inspectors focused their inspection on five plant areas important to safety

July 21, 2016, emergency diesel generator room 1, fire area 35 A August 10, 2016, auxiliary building, fire area August 10, 2016, auxiliary building, fire area August 11, 2016, auxiliary building, fire areas 35A an d 35B August 12, 2016, auxiliary building, fire area For each area, the inspectors evaluated the fire plan against defined hazards and defense-in-depth features in the licensee's fire protection program. The inspectors evaluated control of transient combustibles and ignition sources, fire detection and suppression systems, manual firefighting equipment and capability, passive fire protection features, and compensatory measures for degraded conditions.

These activities constitute d five quarterly inspection sample s , as defined in Inspection Procedure 71111.05.

b. Findings

No findings were identified.

1 R 06 Flood Protection Measures (71111.06)

a. Inspection Scope

On August 9, 2016, the inspectors completed an inspection of the station's ability to mitigate flooding due to internal causes. After reviewing the licensee's flooding analysis, the inspectors chose one plant area containing risk-significant structures, systems, and components that were susceptible to flooding:

Room 22, safety injection pump room The inspectors reviewed plant design features and licensee procedures for coping with internal flooding. The inspectors walked down the selected areas to inspect the design features, including the material condition of seals, drains, and flood barriers. The inspectors evaluated whether operator actions credited for flood mitigation could be successfully accomplished.

These activities constitute d completion of one flood protection measures sample, as defined in Inspection Procedure 71111.06.

b. Findings

No findings were identified.

1 R 07 Heat Sink Performance (71111.07)

a. Inspection Scope

On August 15, 2016 , the inspectors completed an inspection of the readiness and availability of a risk-significant heat exchanger. The inspectors reviewed the data from the performance of spent fuel pool cooling heat exchanger AC-8 disassembly, cleaning, visual inspection, and reassembly activities.

Additionally, the inspectors walked down spent fuel pool cooling heat exchanger AC-8 to observe its performance and material condition and verified that the heat exchanger was correctly categorized under the Maintenance Rule and was receiving the required maintenance.

These activities constitute d completion of one heat sink performance annual review sample , as defined in Inspection Procedure 71111.07.

b. Findings

No findings were identified.

1 R 11 Licensed Operator Requalification Program and Licensed Operator Performance (71111.11)

.1 Review of Licensed Operator Requalification

a. Inspection Scope

On July 26, 2016, the inspectors observed an Emergency Plan drill for an operating crew in the simulator. The inspectors assessed the performance of the operators and the evaluators' critique of their performance. The inspectors also assessed the modeling and performance of the simulator during the requalification activities

. These activities constitute d completion of one quarterly licensed operator requalification program sample , as defined in Inspection Procedure 71111.11.

b. Findings

No findings were identified.

.2 Review of Licensed Operator Performance

a. Inspection Scope

The inspectors observed the performance of on

-shift licensed operators in the plant's main control room.

The inspectors observed the operators' performance of the following activities:

July 5, 2016, operators responded to an automatic isolation of steam generator B blowdown August 10, 2016 , entry into abnormal operating procedure AOP-31 due to 161 k V grid disturbance s August 29, 2016, entry into abnormal operating procedure AOP-12 due to loss of containment integrity September 13, 2016, operators performed an emergency diesel generator 1 surveillance test while conducting fuel moves in the spent fuel pool and diluting the reactor coolant system September 15, 2016, operators respond ed to the failed Loop 2 T hot resistance temperature detector from the B reactor protective system instrument channel In addition, the inspectors assessed the operators' adherence to plant procedures and other operations department policies.

These activities constitute d completion of five quarterly licensed operator performance sample s , a s defined in Inspection Procedure 71111.11.

b. Findings

No findings were identified.

.3 Biennial Review of Requalification Program

a. Inspection Scope

The licensed operator requalification program involves two training cycles that are conducted over a 2

-year period. In the first cycle, the annual cycle, the operators are administered an operating test consisting of job performance measures and simulator scenarios. In the second part of the training cycle, the biennial cycle, operators are administered an operating test and a comprehensive written examination.

To assess the performance effectiveness of the licensed operator requalification program, the inspectors reviewed both the written examination and operating test quality and observed licensee administration of an annual requalification test while onsite. The operating tests observed included five job performance measures and two scenarios that were used in the current biennial requalification cycle. These observations allowed the inspectors to assess the licensee's effectiveness in conducting the operating test to ensure operator mastery of the training program content and to determine if feedback of performance analyses into the requalification training program was being accomplished.

On September 16, 2016, the licensee informed the inspectors of the completed cycle results for Fort Calhoun Station for both the written examinations and the operating tests: 8 of 8 crews passed the simulator portion of the operating test 35 of 38 licensed operators passed the simulator portion of the operating test 36 of 38 licensed operators passed the job performance measure portion of the operating test 34 of 38 licensed operators passed the written examination Two licensed operators did not take any portion of the operating test or written examination. They were unavailable for medical reasons and will be meeting the requalification exam requirements prior to the end of the current biennial cycle ending December 31, 2016.

The individual that failed the simulator scenario portion of the operating test was remediated, retested, and passed their retake test.

Two individuals failed the written examinations. One individual was remediated, retested, and passed their retake examination. The other individual was remediated, retested, and failed their retake examination. On September 26, 2016, the licensee requested that this individual's license be terminated.

The inspectors observed examination security measures in place during administration of the examinatio ns (including controls and content overlap) and reviewed any remedial training and re

-examinations, if necessary. The inspectors also reviewed medical records of five licensed operators for conformance to license conditions and the licensee's system for tracking qualifications and records of license reactivation for one operator.

The inspectors reviewed simulator performance for fidelity with the actual plant and the overall simulator program of maintenance, testing, and discrepancy correction.

The inspectors completed one inspection sample of the biennial licensed operator requalification program.

b. Findings

No findings were identified.

1 R 12 Maintenance Effectiveness (71111.12)

a. Inspection Scope

The inspectors reviewed one instance of degraded performance or condition of safety

-related structures, systems, and components (SSCs): July 28, 2016, spent fuel pool bridge failure The inspectors reviewed the extent of condition of possible common cause SSC failures and evaluated the adequacy of the licensee's corrective actions. The inspectors reviewed the licensee's work practices to evaluate whether these may have played a role in the degradation of the SSCs. The inspectors assessed the licensee's characterization of the degradation in accordance with 10 CFR 50.65 (the Maintenance Rule), and verified that the licensee was appropriately tracking degraded performance and conditions in accordance with the Maintenance Rule.

These activities constitute d completion of one maintenance effectiveness sample , a s defined in Inspection Procedure 71111.12.

b. Findings

No findings were identified.

1 R 13 Maintenance Risk Assessments and Emergent Work Control (71111.13)

a. Inspection Scope

The inspectors reviewed two risk assessments performed by the licensee prior to changes in plant configuration and the risk management actions taken by the licensee in response to elevated risk:

July 8, 2016, planned yellow risk during emergency diesel generator 2 maintenance August 17, 2016, planned yellow risk during emergency diesel generator 1 testing The inspectors verified that these risk assessment s were performed timely and in accordance with the requirements of 10 CFR 50.65 (the Maintenance Rule) and plant procedures. The inspectors reviewed the accuracy and completeness of the licensee's risk assessments and verified that the licensee implemented appropriate risk management actions based on the result of the assessments

. These activities constitute d completion of two maintenance risk assessment inspection samp le s , as defined in Inspection Procedure 71111.13.

b. Findings

No findings were identified.

1 R 15 Operability Determinations and Functionality Assessments (71111.15)

a. Inspection Scope

The inspectors reviewed six operability determinations that the licensee performed for degraded or nonconforming structures, systems, or components (SSCs):

July 15, 2016, operability determination of the primary and secondary control element assemblies following discovery of a degraded condition August 23, 2016, operability determination of the reactor coolant pump RC

-3A motor lower oil reservoir level anomolies August 29, 2016, operability determination of the flooding impact to the raw water pumps not adequately evaluated for the most limiting impact from tornado missile hazards September 2, 2016, operability determination of the raw water pump seal water piping supports not appearing to be seismically qualified September 28, 2016

, operability determination of the boric acid leak on a reactor coolant system sampling line outside containment but inside the reactor coolant system containment isolation valve which affected containment integrity September 29, 2016, assessment of operator work

-arounds The inspectors reviewed the timeliness and technical adequacy of the licensee's evaluations. Where the licensee determined the degraded SSC to be operable, t he inspectors verified that the licensee's compensatory measures were appropriate to provide reasonable assurance of operability. The inspectors verified that the licensee had considered the effect of other degraded conditions on the operability of the degraded SSC

.

The inspectors reviewed operator actions taken or planned to compensate for degraded or nonconforming conditions. The inspectors verified that the licensee effectively managed these operator work

-arounds to prevent adverse effects on the function of mitigating systems and to minimize their impact on the operator s' ability to implement abnormal and emergency operating procedures.

These activities constitute d completion of six operability review samples, which included one operator work

-around sample, a s defined in Inspection Procedure 71111.15.

b. Findings

No findings were identified.

1 R 18 Plant Modifications (71111.18)

a. Inspection Scope

The inspectors reviewed two temporary plant modifications that affected risk

-significant structures, systems, and components (SSCs):

August 24, 2016, tornado protection for raw water system cable pull boxes September 23, 2016, removal of a failed Loop 2 T ho t resistance temperature detector from the B reactor protecti ve system instrument channel The inspectors verified that the licensee had installed these temporary modifications in accordance with technically adequate design documents. The inspectors verified that these modifications did not adversely impact the operability or availability of affected SSCs. The inspectors reviewed design documentation and plant procedures affected by the modifications to verify the licensee maintained configuration contro l. These activities constitute d completion of two sample s of temporary modifications, as defined in Inspection Procedure 71111.18.

b. Findings

No findings were identified.

1 R 19 Post-Maintenance Testing (71111.19)

a. Inspection Scope

The inspectors reviewed five post-maintenance testing activities that affected risk

-significant structures, systems, or components (SSCs):

August 17, 2016, raw water pump AC-10 post-maintenance test September 8, 2016, replace battery charger 3 float potentiometer September 19, 2016, replace time delay agastat relay for component cooling water pump AC

-3B from DC sequencer S 2-1 September 20, 2016, refurbishment of compressed air CA

-1B air compressor September 26, 2016, removal of a failed Loop 2 T hot resistance temperature detector from the B reactor protecti ve system instrument channel The inspectors reviewed licensing- and design

-basis documents for the SSCs and the maintenance and post-maintenance test procedures.

The inspectors observed the performance of the post

-maintenance tests to verify that the licensee performed the tests in accordance with approved procedures, satisfied the established acceptance criteria, and restored the operability of the affected SSCs

. These activities constitute d completion of five post-maintenance testing inspection samples , as defined in Inspection Procedure 71111.19.

b. Findings

No findings were identified.

1 R 22 Surveillance Testing (71111.22)

a. Inspection Scope

The inspectors observed nine risk-significant surveillance tests and reviewed test results to verify that these tests adequately demonstrated that the structures, systems, and components (SSCs) were capable of performing their safety functions:

In-service test s: August 19, 2016, component cooling water pump AC

-3A in-service test September 9, 2016, safety injection/containment spray pumps in-service an d valve exercise test September 30, 2016, raw water pump AC

-10D in-service test Containment isolation valve surveillance tests: July 20, 2016, containment cooler inlet and outlet valves surveillance test Reactor coolant system leak detection tests: September 28, 2016 , reactor coolant system leak detection test Other surveillance tests:

July 15, 2016, emergency diesel generator 1 S1-2 automatic load sequencer surveillance test August 4, 2016, chemical and volume control system boric acid pump CH

-4B surveillance test August 19, 2016, ventilating air system Category A valve exercise surveillance tes t September 20, 2016, diesel driven auxillary feedwater pump FW-54 full flow operability verification test The inspectors verified that these test s met technical specification requirements, that the licensee performed the tests in accordance with their procedures, and that the results of the test s satisfied appropriate acceptance criteria. The inspectors verified that the licensee restored the operability of the affected SSCs following testing.

These activities constitute d completion of nine surveillance testing inspection samples , a s defined in Inspection Procedure 71111.22.

b. Findings

No findings were identified.

Cornerstone:

Emergency Preparedness 1 EP 6 Drill Evaluation (71114.06)

Emergency Preparedness Drill Observation

a. Inspection Scope

The inspectors observed an emergency preparedness drill on July 26, 2016, to verify the adequacy and capability of the licensee's assessment of drill performance. The inspectors reviewed the drill scenario, observed the drill from the simulator, and attended the post-drill critique. The inspectors verified that the licensee's emergency classifications, off

-site notifications, and protective action recommendations were appropriate and timely. The inspectors verified that any recommendations were appropriately identified by the licensee in the post

-drill critique and entered into the corrective action program for resolution.

These activities constitute d completion of one emergency preparedness drill observation sample, as defined in Inspection Procedure 71114.0 6.

b. Findings

No findings were identified.

RADIATION SAFETY

Cornerstones:

Public Radiation Safety and Occupational Radiation Safety 2 RS 1 Radiological Hazard Assessment and Exposure Controls (71124.01)

a. Inspection Scope

The inspectors evaluated th e licensee's performance in assessing the radiological hazards in the workplace associated with licensed activities. The inspectors assessed the licensee's implementation of appropriate radiation monitoring and exposure control measures for both individual and collective exposures. During the inspection, the inspectors interviewed licensee personnel, walked down various areas in the plant, performed independent radiation dose rate measurements, and observed postings and physical controls. The inspectors reviewed licensee performance in the following areas:

Radiological hazard assessment, including a review of the plant's radiological source terms and associated radiological hazards. The inspectors also reviewed the licensee's radiological survey program to determine whether radiological hazards were properly identified for routine and non

-routine activities and assessed for changes in plant operations

.

Instructions to workers including radiation work permit requirements and restrictions, actions for electronic dosimeter alarms , changing radiological condition, and radioactive material container labeling.

Contamination and radioactive material control

, including release of potentially contaminated material from the radiologically controlled area, radiological survey performance, radiation instrument sensitivities, material control and release criteria, and control and accountability of sealed radioactive sources.

Radiological hazards control and work coverage. During walk

-downs of the facility and job performance observations, the inspectors evaluated ambient radiological conditions, radiological postings, adequacy of radiological controls, radiation protection job coverage, and contamination controls. The inspectors also evaluated dosimetry selection and placement as well as the use of dosimetry in areas with significant dose rate gradients. The inspectors examined the licensee's controls for items stored in the spent fuel pool and evaluated airborne radioactivity controls and monitoring.

High radiation area and very high radiation area controls. During plant walk-downs, the inspectors verified the adequacy of posting and physical controls, including areas of the plant with the potential to become risk

-significant high radiation areas.

Radiation worker performance and radiation protection technician proficiency with respect to radiation protection work requirements. The inspectors determined if workers were aware of significant radiological conditions in their workplace, radiation work permit controls/limits in place, and electronic dosimeter dose and dose rate set points. The inspectors observed radiation protection technician job performance, including the performance of radiation surveys.

Problem identification and resolution for radiological hazard assessment and exposure controls. The inspectors reviewed audits, self

-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.

These activities constitute d completion of the seven required samples of radiological hazard assessment and exposure control program, as defined in Inspection Procedure 71124.01.

b. Findings

No findings were identified.

2 RS 5 Radiation Monitoring Instrumentation (71124.05)

a. Inspection Scope

The inspectors evaluated the accuracy and operability of the radiation monitoring equipment used by the licensee to monitor areas, materials, and workers to ensure a radiologically safe work environment. This evaluation included equipment used to monitor radiological conditions related to normal plant operations, anticipated operational occurrences, and conditions resulting from postulated accidents. The inspectors interviewed licensee personnel, walked down various portions of the plant, and reviewed licensee performance associated with radiation monitoring instrumentation, as described below: The inspectors performed walk

-downs and observations of selected plant radiation monitoring equipment and instrumentation, including portable survey

instruments, area radiation monitors, continuous air monitors, personnel contamination monitors, portal monitors, and small article monitors. The inspectors assessed material condition and operability, evaluated positioning of instruments relative to the radiation sources or areas they were intended to monitor, and verified performance of source checks and calibrations

.

The inspectors evaluated the calibration and testing program, including laboratory instrumentation , whole body counters , post-accident monitoring instrumentation, portal monitors, personnel contamination monitors, small article monitors , portable survey instruments, area radiation monitors , electronic dosimetry , air samplers, and continuous air monitors

.

The inspectors assessed problem identification and resolution for radiation monitoring instrumentation. The inspectors reviewed audits, self

-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.

These activities constitute d completion of the three required samples of radiation monitoring instrumentation, as defined in Inspection Procedure 71124.05.

b. Findings

No findings were identified.

2RS6 Radioactive Gaseous and Liquid Effluent Treatment

Main article: IP 71124.06

a. Inspection Scope

The inspectors evaluated whether the licensee maintained gaseous and liquid effluent processing systems and properly mitigated, monitored, and evaluated radiological discharges with respect to public exposure. The inspectors verified that abnormal radioactive gaseous or liquid discharges and conditions, when effluent radiation monitors are out-of-service, were controlled in accordance with the applicable regulatory requirements and licensee procedures. The inspectors verified that the licensee's quality control program ensured radioactive effluent sampling and analysis adequately quantified and evaluated discharges of radioactive materials. The inspectors verified the adequacy of public dose projections resulting from radioactive effluent discharges. The inspectors interviewed licensee personnel and reviewed licensee performance in the following areas:

During walk-downs and observations of selected portions of the radioactive gaseous and liquid effluent equipment, the inspectors evaluated routine processing and discharge of effluents, including sample collection and analysis. The inspectors observed equipment configuration and flow paths of selected gaseous and liquid discharge system components , effluent monitoring systems, filtered ventilation system material condition, and significant changes to effluent release points.

Calibration and testing program for process and effluent monitors, including National Institute of Standards and Technology (NIST) traceability of sources , primary and secondary calibration data, channel calibrations, set-point determination bases, and surveillance test results

.

Sampling and analysis controls used to ensure representative sampling and appropriate compensatory sampling. Reviews included results of the inter

-laboratory comparison program

.

Instrumentation and equipment, including effluent flow measuring instruments, air cleaning systems, and post

-accident effluent monitoring instruments.

Dose calculations for effluent releases. The inspectors reviewed a selection of radioactive liquid and gaseous waste discharge permits and abnormal gaseous or liquid tank discharges, and verified the projected doses were accurate. The inspectors also reviewed 10 CFR Part 61 analyses and methods used to determine which isotopes were included in the source term. The inspectors reviewed land use census results, offsite dose calculation manual changes, and significant changes in reported dose values from previous years.

Problem identification and resolution for radioactive gaseous and liquid effluent treatment. The inspectors reviewed audits, self-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.

These activities constitute d completion of the six required samples of radioactive gaseous and liquid effluent treatment program, as defined in Inspection Procedure 7112 4.0 6.

b. Findings

No findings were identified.

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

a. Inspection Scope

The inspectors evaluated the effectiveness of the licensee

's programs for processing, handling, storage, and transportation of radioactive material.

The inspectors interviewed licensee personnel and reviewed the following items:

Radioactive material storage, including waste storage areas including container labeling/marking and monitoring containers for deformation or signs of waste decomposition

. Radioactive waste system

, including walk

-downs of the accessible portions of the radioactive waste processing systems and handling equipment. The inspectors also review ed or observed changes made to the radioactive waste processing systems, methods for dewatering and waste stabilization, waste stream mixing methodology, and waste processing equipment that was not operational or abandoned in place

. Waste characterization and classification

, including radio-chemical sample analysis results for radioactive waste streams and use of scaling factors and calculations to account for difficult

-to-measure radionuclides, and processes for waste classification including use of scaling factors and 10 CFR Part 61 analyses. Shipment preparation, including packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and preparation of the disposal manifest s. Shipping records for LSA I, II, III, SCO I, II, Type A, or Type B radioactive material or radioactive waste shipments.

Problem identification and resolution for radioactive solid waste processing and radioactive material handling, storage, and transportation. The inspectors reviewed audits, self

-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.

These activities constitute d completion of the six required samples of radioactive solid waste processing and radioactive material handling, storage, and transportation

program, as defined in Inspection Procedure 71124.08.

b. Findings

No findings were identified.

OTHER ACTIVITIES

Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness, Public Radiation Safety, Occupational Radiation Safety, and Security 4OA 1 Performance Indicator Verification (71151)

.1 Mitigating Systems Performance Index

High Pressure Injection Systems (MS07)

a. Inspection Scope

The inspectors reviewed the licensee's mitigating system performance index data for the period of July 1, 2015 , through June 30, 2016, to verify the accuracy and completeness of the reported data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.

These activities constituted verification of the mitigating system performance index for high pressure injection systems, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.2 Mitigating Systems Performance Index

Heat Removal System s (MS08)

a. Inspection Scope

The inspectors reviewed the licensee's mitigating system performance index data for the period of July 1, 2015, through June 30, 2016, to verify the accuracy and completeness of the reported data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.

These activities constituted verification of the mitigating system performance index for heat removal systems, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.3 Mitigating Systems Performance Index

Cooling Water Support Systems (MS10)

a. Inspection Scope

The inspectors reviewed the licensee's mitigating system performance index data for the period of July 1, 2015, through June 30, 2016, to verify the accuracy and completeness of the reported data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.

These activities constituted verification of the mitigating system performance index for cooling water support systems, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.4 Occupational Exposure Control Effectiveness (OR01)

a. Inspection Scope

The inspectors verified that there were no unplanned exposures or losses of radiological control over locked high radiation areas and very high radiation areas during the period of April 1, 2015, to June 30, 2016. The inspectors reviewed a sample of radiologically controlled area exit transactions showing exposures greater than 100 millirem. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7 , to determine the accuracy of the reported data.

These activities constituted verification of the occupational exposure control effectiveness performance indicator

, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.5 Radiological Effluent Technical Specifications (RETS)/Offsite Dose Calculation Manual (ODCM) Radiological Effluent Occurrences (PR01)

a. Inspection Scope

The inspectors reviewed corrective action program records for liquid or gaseous effluent releases that occurred between April 1, 2015 , and June 30, 2016, and were reported to the NRC to verify the performance indicator data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, to determine the accuracy of the reported data.

These activities constituted verification of the radiological effluent technical specifications (RETS)/offsite dose calculation manual (ODCM) radiological effluent occurrences performance indicator

, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

4OA 2 Problem Identification and Resolution (71152)

.1 Routine Review

a. Inspection Scope

Throughout the inspection period, the inspectors performed daily reviews of items entered into the licensee's corrective action program and periodically attended the licensee's condition report screening meetings. The inspectors verified that licensee personnel were identifying problems at an appropriate threshold and entering these problems into the corrective action program for resolution. The inspectors verified that the licensee developed and implemented corrective actions commensurate with the significance of the problems identified.

The inspectors also reviewed the licensee's problem identification and resolution activities during the performance of the other inspection activities documented in this report.

b. Findings

No findings were identified.

.2 Annual Follow

-up of Selected Issues

a. Inspection Scope

The inspectors selected one issue for an in-depth follow-up: On September 30, 2016 , in leakage into safety injection tank 6A.

The inspectors assessed the licensee's problem identification threshold, cause analyses, extent of condition reviews and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition.

These activities constitute d completion of one annual follow-up sample a s defined i n Inspection Procedure 71152.

b. Findings

No findings were identified.

4OA 3 Follow-up of Events and Notices of Enforcement Discretion (71153)

.1 Plant Events

a. Inspection Scope

For the plant events listed below, the inspectors reviewed and observed plant parameters, reviewed personnel performance, and evaluated performance of mitigating systems as applicable. The inspectors communicated the plant events to appropriate regional personnel, and compared the event details with criteria contained in Inspection Manual Chapter 0309, "Reactive Inspection Decision Basis for Reactors," for consideration of potential reactive inspection activities. As applicable, the inspectors verified that the licensee made appropriate emergency classification assessments and properly reported the event in accordance with 10 CFR 50.72 and 50.73. The inspectors reviewed the licensee's follow

-up actions related to the event to assure that the licensee implemented appropriate corrective actions commensurate with their safety significance.

August 10, 2016, operator response to 161 kV grid disturbances August 29, 2016, operator response to a loss of containment integrity September 3, 2016, operator response to a seismic event alarm

b. Findings

No findings were identified.

.2 (Closed) Licensee Event Report 05000285/2016

00 , "Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor"

a. Inspection Scope

On February 1 0, 2016 , the licensee became aware of a 10 CFR 21.21 nonconformance notification issued by Canberra Industries, Incorporated. Canberra identified that some components from purchase orders associated with radiation monitors had not fully met 10 CFR 50.49 electrical equipment qualification standard s. It was determined that certain components (time delay, mass flow controller, and vacuum pump motor) in specific radiation monitors (RMs)

-50, -51, and -52 may not be qualified for the potential worst case environmental conditions during an electromagnetic, high temperature or seismic event. By February 12, 2016, t he licensee and Canberra located the components that should have been included in the electrical equipment qualification program. Eventually, the licensee determined that only RM

-52 (auxiliary building vent stack monitor) had an unqualified part installed, a time delay relay.

The licensee did not have the nonconforming relay rededicated or requalified. As corrective action, the licensee replaced the relay with a new relay that had been properly qualified. The extent of condition evaluation revealed that when RM

-52 was in the degraded condition with the unqualified time delay relay, it was relied on to backup the dedicated containment building radiation monitors RM

-50, -51, and -62. These radiation monitors provide a containment radiation high signal during an event and are required to be operable per Technical Specification 2.15.1. The licensee corrected the deficiency immediately upon notificatio n and no additional deficiencies were identified during the review of this licensee event report. Therefore, the inspector determined there was no performance deficiency. This licensee event report is closed.

b. Findings

No findings were identified.

.3 (Closed) Violation 05000285/2015010-01, "Failure to Provide Complete and Accurate Information on Licensed Operator Applications"

The NRC issued this cited violation of 10 CFR 50.9, "Completeness and Accuracy of Information," for the Fort Calhoun Station's failure to perform combustion odor testing as required in American National Standards Institute Standard 3.4-1996 for physical examinations of licensed operators and as documented in NRC Form 396, "Certification of Medical Examination by Facility Licensee." To address this violation, the licensee initiated Condition Report C R 2014-05108. The inspectors reviewed the actions documented in Condition Report CR 2014-05108 and the subsequent condition reports. Those corrective actions included testing all licensed operators for combustion odor testing prior to taking their next scheduled watch, and revising Procedure OP

-AA-105-101, "Administrative Process for NRC License and Medical Requirements," to bring the Exelon fleet model to Fort Calhoun Station. The inspectors determined that through these actions, the licensee restored compliance to 10 CFR 55.23. This violation is closed.

These activities constitute d completion of five event follow

-up samples, as defined in Inspection Procedure 71153.

4OA5 Other Activities Follow Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the

Same Area in a 12

-Month Period

a. Inspection Scope

The inspectors performed Inspection Procedure (IP)92723, "Follow Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12-Month Period," based on the results of the NRC's mid

-cycle assessment review of station performance as documented in the 2015 mid

-cycle assessment letter dated September 1, 2015. From July 1, 2014 through J une 30, 2015, the NRC issued eight Severity Level (SL) IV traditional enforcement violations in the area of impeding the regulatory process, four of which involved the implementation of the 10 CFR 50.59 process.

The inspectors reviewed the licensee's cause evaluation and corrective actions associated with these issues in order to determine whether the licensee's actions met the IP 92723 inspection objectives to provide assurance that:

(1) the cause(s) of the violations are understood by the licensee; (2)the extent of condition and extent of cause of the violations are identified; and (3)licensee corrective actions to the violations are sufficient to address the cause(s).

b. Observations and Findings

The licensee determined the cause was leadership had not provided adequate governance and oversight to influence behaviors and hold personnel accountable. The licensee also determined that the traditional enforcement issues were driven by human performance errors and were primarily associated with the implementation of the 10 CFR 50.59 process by engineering personnel. The licensee reviewed traditional enforcement violations from the previous 12

-month time period and identified similar issues and drivers (e.g., several 10 CFR 50.59 process implementation issues). The inspectors determined the SLIV violations received an evaluation at an appropriate level of detail to identify the causes and included review of prior occurrences. The inspectors also conclude d the evaluation of the traditional enforcement violations included an appropriate extent of condition and extent of cause of the issues.

The licensee credited several high level corrective actions previously implemented during their recovery while in the Inspection Manual Chapter 0350 process. These actions included; development of governance and oversight policies and transition to t he Exelon Management model, implementation of a new engineering organizational structure, development and implementation of an Institute of Nuclear Power Operations (INPO) Human Performance Strategic Plan, and the development of an interim Engineering Assurance Group to review engineering product quality. In addition, actions were taken specifically to improve engineering performance and 10 CFR 50.59 process implementation. The actions included 10 CFR 50.59 training, limiting the number of personnel qualified to perform 10 CFR 50.59 evaluations and reviews

, and the development of key performance indicators to trend the quality of these engineering products. The inspectors determined these corrective actions were comprehensive and appropriate to improve overall site performance and specifically to improve 10 CFR 50.59 process and engineering department performance. The inspectors also determined that the corrective actions were prioritized and implemented on a schedule reflective of the organizational turn around necessary to improve site performance. The inspectors noted that although some actions had not appeared to have been in place long enough to effectively preclude the traditional enforcement violations that were identified in the 2014 to 2015 time period, overall site and specifically engineering performance has improved since this time

.

The licensee identified several success measures to determine the effectiveness of the traditional enforcement corrective actions including: verification of the completion of engineering training classes, a Nuclear Oversight department audit of the design process (including the 10 CFR 50.59 process with no findings), a successful check

-in self-assessment conduc ted in June 2016, and an overall reduction of traditional enforcement violations in the 12 months following the period of the review (two traditional enforcement violations issued

, one of which involved the 10 CFR 50.59 process). The inspectors determined that the licensee developed measures of success which reasonably show improvement has occurred and that corrective actions were reasonably affective in preventing recurrence.

No findings were identified.

4OA 6 Meetings, Including Exit

Exit Meeting Summary

On July 22, 2016, the inspectors presented the radiation safety inspection results to Mr. M. Prospero, Vice President, Site (Acting), and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.

On September 28, 2016, the inspectors briefed Mr. S. Marik, Vice President and Chief Nuclear Officer, and other members of the licensee's staff of the results of the licensed operator requalification program inspection. The licensee representatives acknowledged the findings presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.

On October 12, 2016, the inspectors presented the inspection results to Mr. M. Prospero , Acting Site Vice President, and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

A. Barker, Supervisor, Radiation Protection
C. Beck, Director, Training, (Acting)
R. Beck, Manager Chemistry, Environmental, and Radwaste
A. Beebe, Supervisor, Chemistry
B. Blessie, Operations Training
B. Blome, Manager, Regulatory Assurance
B. Bonwell, Requalification Supervisor
E. Breault, Supervisor, Radiological Operations
D. Brehm, Supervisor, Radiation Protection Technical Support
C. Cameron, Principal

Regulatory Specialist

J. Cate, Manager, Engineering Projects
H. Childs, Manager, Security
D. Conn, Shipper, Radiation Protection
B. Currier, Director, Site Engineering
E. Durboraw, Specialist, Radwaste
E. Engert, Senior Technician, Chemistry
J. Hoffman, Supervisor, Chemistry
R. Hugenroth, Manager, Nuclear Oversight
K. Kingston, Director Maintenance (Acting)
T. Leaf, Director, Operations
L. Maine, Senior Technician, Chemistry
S. Marik, Vice President and Chief Nuclear Officer
E. Matzke, Senior Licensing Engineer
T. Parent, Engineering
B. Pearson, Supervisor, Radiation Protection
E. Plautz, Manager, Emergency Planning
M. Prospero, Vice President, Site (Acting)
A. Ritton, Senior Technician, Chemistry
J. Shuck, Manager, Systems Engineering
J. St. Claire, Operations Training
J. Sunderman, Senior Radiation Protection Technician
T. Tierney, Plant Manager
T. Uehling, Manager, Training
C. Verdoni, Operation Training
D. Weaver, Director, Site Work Management (Acting)
D. Whisler, Manager, Radiation Protection

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Closed

05000285/2016
001-00 LER Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor

(Section 4OA3)

05000285/2015010

-01 VIO Failure to Provide Complete and Accurate Information on Licensed Operator Applications

(Section 4OA3)

LIST OF DOCUMENTS REVIEWED

Section 1R01: Adverse Weather Protection

Procedures

Number Title Revision
AOP-1 Acts of Nature
OP-AA-108-111-1001 Severe Weather and Natural Disaster Guidelines
SO-G-119 Site Wind Generated Missile Protection Standards Section 1R04
Equipment Alignment

Miscellaneous

Documents Number Title Revision/Date Maintenance Rule Functional Scoping Data Sheets for Spent Fuel Pool Cooling System

Drawings

Number Title Revision 11405-M-10 Auxiliary Coolant Component Cooling System P&ID
11405-M-10 Auxiliary Coolant Component Cooling System Flow Diagram P&ID, Sheet
22 11405-M-10 Auxiliary Coolant Component Cooling System Flow Diagram P&ID, Sheet
27 11405-M-40 Auxiliary Coolant Component Cooling System P&ID
11405-M-11 Spent Fuel Pool Cooling System Flow Diagram
11405-M-252 Steam P&ID, Sheet
116 11405-M-253 Steam Generator Feedwater and Blowdown P&ID, Sheet 4 42 11405-M-254 Condensate
P&ID, Sheet
43

Miscellaneous

Documents Number Title Revision/Date Spent Fuel Pool Cooling System Health Report April 1, 2016 to July 31, 2016
Summary Report of Spent Fuel Pool Cooling System Condition Reports
2015 - 2016
Boric Acid Corrosion Control Program Spent Fuel Pool Cooling System Open Leak List August 17, 2016
Chapter 9.6 Updated Safety Analysis Report (USAR), Spent Fuel Pool Cooling System

Procedures

Number Title Revision
OI-AFW-1 Auxiliary Feedwater Actuation System Normal Operation
OI-CC-1 Component Cooling System Normal Operation
OI-DG-2 Operating Instruction Diesel Generator No. 2
OI-SFP-1 Spent Fuel Pool Cooling Normal Operation
OP-ST-AFW-0001 Auxiliary Feedwater System Valve Alignment Check
SO-G-123 Protected Equipment Program

Condition Reports

(CRs)

2016-05807 2014-01969
Section 1R05
Fire Protection

Miscellaneous

Documents Number Title Revision Chapter 9.11 Updated Safety Analysis Report (USAR), Auxiliary Systems Fire Protection System
25, 28

Procedures

Number Title Revision
AOP-06-02 Uncontrolled Areas of Auxiliary Building
EA-97-001 Updated Fire Hazards Analysis
SO-G-28 Standing Order Station Fire Plan
SO-G-102 Fire Protection Program Plan

Procedures

Number Title Revision
UFHA-EA97-001 Fire Area 43 EFWST Area (room 81)

Condition Reports

(CRs)

2014-08637 2016-05807
Section 1R06
Flood Protection Measures Miscellaneous

Documents

Number Title Revision
PRA Summary Notebook Calculation
EA 08-010 Internal Flooding Calculation
EA 92-057 Internal Flood Analysis Report
FC08313 Calculation, Fort Calhoun Room 81 Flooding Analysis 0

Procedures

Number Title Revision
ARP-AI-100/A50 Annunciator Response Procedure A50 Local Annunciator A50, Waste Disposal Section 1R07
Heat Sink Performance

Drawings

Number Title Revision B-4298 Temporary Spent Fuel Pool Cooling System, Sheet 1
B-4298 Temporary Spent Fuel Pool Cooling System, Sheet 2
11405-M-11 Temporary Spent Fuel Pool Cooling System Flow Diagram

Miscellaneous

Documents Number Title Revision/Date Spent Fuel Pool Cooling System Health Report April1, 2016 to July 31, 2016
Maintenance Rule Functional Scoping Data Sheets for Spent Fuel Pool Cooling System

Miscellaneous

Documents Number Title Revision/Date Chapter 4.5.6.5 Updated Safety Analysis Report (USAR), In

-Service Inspection of ASME Code Class 1, Class 2, and Class 3 Components Chapter 9.6 Updated Safety Analysis Report (USAR), Spent Fuel Pool Cooling System Preliminary Report 18-57 Fuel Pool Cooler AC

-8, Integrated Technologies, Inc.

March 21, 2005

Procedures

Number Title Revision
OI-SFP-1 Spent Fuel Pool Cooling Normal Operation
QC-ST-SFP-3001 Forty Month In

-Service Test of the Spent Fuel Pool Cooling System in Room number 5

Condition Reports

(CRs)

2016-05807

Work Orders

Number Title
00188897 Task 01, IC

-8 Remove Channel Cover, Inspect, Reinstall Cover

00201320 Task 01, Plug 15 U

-Tubes in AC

-8 Hx

00413547 Task 01, Perform the Procedure SE

-PFT-CCW-004

Section 1R11: Licensed Operator Requalification Program

and Licensed Operator Performance

Miscellaneous Documents

Number Title Revision/Date
Control Room Logs
2015 - Week 1 Annual Operating Test (2
Scenarios, 5 Job Performance Measures)
2015
2015 - Week 2 Annual Operating Test (2 Scenarios, 5 Job Performance Measures)
2015
2016 - LORT 2016, Rotation 5, Week 3 RO Written Exam
2016
2016 - LORT 2016, Rotation 5, Week 3 SRO Written Exam
2016

Miscellaneous Documents

Number Title Revision/Date
2016 - Week 3 Annual Operating Test (2 Scenarios, 5 Job Performance Measures)
2016
2016 - Week 4 Annual Operating Test (2 Scenarios, 5 Job Performance Measures)
2016
Post Event Simulator Tes

t December 17, 20 14

Post Event Simulator Test March 17, 20 14
Post Event Simulator Test July 27, 20
Simulator Work Requests

- open and closed from last two years 2015-2016 2.6 Technical Specification, Containment System

CFR 55.46
Simulator Facilities January 1, 2016 161F561 SPEC 200 Loop Diagram:
Loop B/TE

-112C, B/TE

-112H, B/TE-122C, B/TE

-122H 47 17391 Emergency Generators Schematic Diagram

68913 Engineering Change, Remove B/TE

-122H from RPS

September 17, 2016 ANSI/ANS-3.4 Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants
1996 Chapter 12.1 Updated Safety Analysis Report (USAR), Conduct of Operations

- Organization and Responsibilities Chapter 12.2 Updated Safety Analysis Report (USAR), Conduct of Operations

- Training 5 Chapter 12.6 Updated Safety Analysis Report (USAR), Conduct of Operations

- Site Emergency Plan

IP-71111.11 Appendix G and H, effective date Jan 1, 2015
RERP Radiological Emergency Response Plan

Procedures

Number Title Revision/Date
AOP-12 Loss of Containment Integrity
AOP-31 161 kV Grid Disturbances

Procedures

Number Title Revision/Date
ARP-CB-1,2,3/A4 Annunciator Lampbox A4 Control Board CB

-1/2/3 Power

AI-41B 36
ARP-CB-4/A20 Annunciator Lampbox A20 Control Board CB

-4 Power

AI-41A 48
HR-AA-07-101 N RC Licensed Operator Medical Examination
OI-FW-5 Steam Generator Blowdown Normal Operation
OP-AA-101-113 Operator Fundamentals
OP-AA-103-102 Watch-Standing Practices
OP-AA-103-103 Operation of Plant Equipment
OP-AA-104-101 Communications
OP-AA-105-101 Administrative Process for NRC License and Medical Requirements
OP-AA-105-102 NRC Active License Maintenance
OP-ST-DG-0001 Diesel Generator 1 Check
OP-ST-RPS-0005 RPS Power Adjustment
STM-RR Volume 36, RCS Instrumentation and Reactor Regulating Systems 24
SY-FC-102-206 Reporting Use of Medication
TBD-EOP-05 Uncontrolled Heat Extraction
TQ-AA-150 Operator Training Programs
TQ-AA-155 Conduct of Simulator Training and Evaluation
TQ-AA-201 Examination Security and Administration
TQ-AA-223 Required Reading Training Package

- Deboration and Coastdown Overview August 29, 20 16

TQ-FC-201-J01, App A Licensed Operator Training Simulator Checklist (FCS Specific) 1
TQ-FC-306 Simulator Management
TQ-FC-SS-50 Simulator Steady State Test

- 50%

1
TQ-FC-TR-1 Manual Reactor Trip Simulator Testing
TQ-FC-TR-10 Slow Primary System Depressurization to Saturated Condition using PORV
TQ-FC-TR-11 Maximum Design Load Rejection Simulator Testing 3

Procedures

Number Title Revision/Date
TQ-FC-TR-6 Turbine Trip from Maximum Power Level does not result in Immediate Reactor Trip
TQ-FC-TR-8 Maximum Size RCS Rupture with Loss of Offsite Power Simulator Testing
TQ-FC-TR-9 Maximum Size Unisolable MSLR Simulator Testing

Work Orders

Number Title
00576848 Task 01, Diesel Generator 1 Check

Condition Reports

(CRs)

2013-21774 2014-00376 2014-00379 2014-09652 2014-09655 2014-10116 2014-10172 2014-10297 2014-10573 2014-10907 2014-10938 2014-11396 2014-11546 2014-11840 2014-11938 2014-12020 2014-12693 2014-13632 2014-13878 2014-15294 2015-00810 2015-01033 2015-01277 2015-02181 2015-02940 2015-03599 2015-03621 2015-04442 2015-06224 2015-07522 2015-08240 2015-08243 2015-08246 2015-09200 2015-09308 2015-09618 2015-09638 2015-09795 2015-10566 2015-10572 2015-11215 2015-11707 2015-12496 2015-12863 2015-12964 2015-13125 2015-13324 2015-13738 2015-13800 2015-14282 2016-00516 2016-01239 2016-01531 2016-02035 2016-02777 2016-03429 2016-03700 2016-03786 2016-04032 2016-04415 2016-04468 2016-04756 2016-05256 2016-05471 2016-05807 2016-06039 2016-07037 2016-07038 2016-07045 2016-07333 2016-07336 2016-07388
Section 1R12
Maintenance Effectiveness

Procedures

Number Title Revision
ER-AA-310 Implementation of the Maintenance Rule
ER-AA-310-1001 Maintenance Rule Scoping

Procedures

Number Title Revision
ER-AA-310-1002 Maintenance Rule Functions

- Safety Significance Classification

ER-AA-310-1003 Maintenance Rule

- Performance Criteria Selection

Condition Reports

(CRs)

2016-04448 2016-04013 2016-03970 2016-06117 2015-05313 2015-05404 2015-04842
Section 1R13
Maintenance Risk Assessments and Emergent Work Control

Miscellaneous

Documents Number Title Revision
Equipment Out Of Service Quantitative Risk Assessment Tool
Chapter 8.4 Updated Safety Analysis Report (USAR), Emergency Power Sources 19
WC-AA-101 Attachment 7
High Risk Evolution Determination

Procedures

Number Title Revision
ER-AA-600 Risk Management
ER-AA-600-1011 Risk Management Administrative Guidance 15
ER-AA-600-1042 On-line Risk Management
PO-ST-DG-0001 Surveillance Test

- Diesel Generator 1 Check

SO-G-123 Protected Equipment Program

Condition Reports

(CRs)

2016-05807
Section 1R15
Operability Determinations and Functionality Assessments

Miscellaneous Documents

Title Revision/Date
Adverse Condition Monitoring Plan, RC

-3A Reactor Coolant Pump Motor Lower Oil Reservoir Level Indication August 15, 2016

Event Notification for an Unanalyzed Condition that Significantly Degrades Plant Safety and a Condition that could have Prevented Fulfillment of a Safety Function August 25, 2016
Fort Calhoun Site Risk Issue Summary Report September 28, 2016
Fort Calhoun Site Risk Map September 28, 2016
Operator Burden Backlog Report September 26, 2016
Plant Health Committee Meeting Minutes July 20, 2016 and August 17, 2016
RC-3A Lower Oil Reservoir Level versus Containment Pressure Plots
50.59 Review for
EC 68845/OP Eval 16

-003

2.6 Technical Specification, Containment System
68845 Engineering Change, RW Vault Flooding Due to FP Tornado Missile Strike Chapter 5.9 Updated Safety Analysis Report, Containment Penetrations Chapter 9.13 Updated Safety Analysis Report, Auxiliary Systems

-Sampling Systems Chapter 9.8 Updated Safety Analysis Report, Raw Water System

FC06343 Calculation, Input, Stress Analysis, and Qualification of Piping for Seismic Subsystem RW

-4264, Raw Water Pump Seal Water Supply

0A FC08264 Calculation, Seismic Qualification of Raw Water Pump Seal Water Supply Pipe Supports

-

SWS-15,
SWS-17,
SWS-19, and
SWS-21 0

Procedures

Number Title Revision
AOP-12 Loss of Containment Integrity
AOP-35 Reactor Coolant Pump Malfunctions

Procedures

Number Title Revision
OI-RC-9 Reactor Coolant Pump Operation
OI-RW-1 Raw Water System Normal Operation
111
OP-AA-102-103 Operator Work

-Around Program

OP-AA-102-103-1001 Operator Burden and Plant Significant Decision Impact Assessment Program
OP-AA-108-111 Adverse Condition Monitoring and Contingency Plan, Attachment
10
OP-FC-108-105-1001 MCR and RWCR Equipment Deficiency Management and Performance Indicator Screening
OP-FC-108-115 Operability Determinations
OP-FC-108-115-AD-ODQRB Operability Determination Oversight and Monitoring
OP-ST-SHIFT-0001 Operations Technical Specification Required Shift Surveillance
2

Condition Reports

(CRs)

2013-16870 2015-07764 2015-09481 2016-05571 2016-05847 2016-06752 2016-06972 2016-07037 2016-07038 2016-07060 2016-07140 2016-07395 2016-07396 2016-07560 2016-07643
Section 1R18
Plant Modifications

Miscellaneous Documents

Number Title Revision/Date
Operability Evaluation for CR

-2016-06498

1.76 Regulatory Guide, Design Basis Tornado and Tornado Missiles for Nuclear Power Plant, March 2007
2.15.1 Technical Specification, Instrumentation and Control Systems
50.59 Review for
EC 68783/Op Eval 16

-002 August 8, 2016 50.59 Screening Form for EC 68783

August 8, 2016 60183 Engineering Change, Tornado Protection for Pull Boxes
PB-128T and
PB-129T 3

Miscellaneous Documents

Number Title Revision/Date 68913 Engineering Change, Remove B/TE

-122H from RPS

Chapter 7.1
Updated Safety Analysis Report (USAR), Instrumentation and Control Chapter 7.2
Updated Safety Analysis Report (USAR), Reactor Protective Systems Instrumentation Systems
16, 27
EM-122 Drawing, Instrument and Control Equipment List, Sheet 1
FC08250 Design Analysis, Tornado Pr otection for Pull Boxes
PB-128T and
PB-129T 3
SK-EC60183-01 Drawing, Tornado Missile Barrier for Pull Boxes PB

-12 8 T and

PB-129T E

Procedures

Number Title Revision
CC-AA-112 Temporary Configuration Changes
LS-AA-104 Exelon 50.59 Review Process
OP-AA-108-115 Operability Determinations (CM

-1) 18

OP-ST-RPS-0005 RPS Power Adjustment
OP-ST-SHIFT-0001 Operations Technical Specification Required Shift Surveillance
2

Condition Reports

(CRs)

2016-05807 2015-06498 2016-07333 2016-07376 2016-07433

Work Orders

Number Title
00593556 Task 02, B/TI-122H; Perform Troubleshooting per
MA-AA-716-004
Section 1R19
Post-Maintenance Testing

Miscellaneous Documents

Number Title Revision
Electrical Troubleshooting Log August 31, 2016

Miscellaneous Documents

Number Title Revision
Diesel Generator Sequence

r Report September 1, 2016

Maintenance Alterations Log for WO 00592537

-02 September 1, 2016 161F598 Drawing, AI

-30B DC Sequencer S2

-1 Auto Start Circuit 480V Bus 1B4C and Bus Tie 1B3C

-4C, Sheet 2

20751 Drawing, Schematic 125
Vdc Battery Charger
20778 Drawing, Battery Chargers EE

-8C, 8D, 8E

68913 Engineering Change, Remove B/TE

-122H from RPS 2 E-4126 Drawing, Logic Diagram Panels AI

-30A & B, DC Sequencers S1

-1 & S2-1, and AC Sequencers S1

-2 & S2-2 6

EM-122 Drawing, Instrument and Control Equipment List, Sheet
14

Procedures

Number Title Revision
EM-RR-EE-0812 Maintenance of Battery Charger

(EE-8E) Alarm Cards

MA-AA-716-012 Post Maintenance Testing
MD-RR-EX-1000 Soldering Guidelines for Electronic Components
MM-PM-PX-0051 Air Compressor CA

-1A,

CA-1B, and CA

-1C Maintenance

OP-ST-EE-0002 Monthly Surveillance Test for Station Battery Chargers
OP-ST-ESF-0010 Channel B Safety Injection, Containment Spray, and Recirculation Actuation Signal Test
OP-ST-RPS-0005 RPS Power Adjustment
OP-ST-RW-3005 Raw Water Pump Post Maintenance Operability Test 3
OP-ST-SHIFT-0001 Operations Technical Specifications Required Shift Surveillance
2
OP-ST-SI-3022 Safety Injection/Containment Spray Pumps and Valve Exercise In

-Service Test, Room 22

Work Orders

Number Title
00573833 Task 01, CA

-1B; Inspection and Refurbishment

MM-PM-PX-0051

Work Orders

Number Title
00578183 Task 01, EE

-8E; Conduct Alarm Card Maintenance

00591545 Task 01, EE

-8E; Replace Float Potentiometer

00591969 Task 01, EE

-8E; Replace CFA Board and DSL Board for Battery Charger #3

00592537 Task 02, Replace Time Delay Pick Up Relay on Sequencer S2-1 for
AC-3B
00593556 Task 02, B/TI-122H; Perform Troubleshooting per
MA-AA-716-004

Condition Reports

(CRs)

2016-05807 2016-06787 2016-06677 2016-06959
Section 1R22
Surveillance Testing

Drawings

Number Title Revision E-23866-210-120 Piping & Instrumentation Diagram

- CVCS 15 E-23866-210-121 Piping & Instrumentation Diagram

- CVCS 15

Miscellaneous

Documents Number Title Revision/Date
Control Room Logs Technical Specification 3.1, Instrumentation and Control Surveillance Requirements, Table 3

-2

Updated Safety Analysis Report (USAR), Chapter 8.4, Emergency Power Sources Updated Safety Analysis Report (USAR), Chapter 7.3, Engineered Safeguards Controls and Instrumentation
2.2 Technical Specification, Chemical and Volume Control System 249 Amendment 165
NRC Safety Evaluation August 25, 1994 Chapter 9.2
Updated Safety Analysis Report (USAR), Chemical and Volume Control System
FC05462 Response Time of Containment Air Monitoring System

Miscellaneous

Documents Number Title Revision/Date FC05464 Sensitivity of Containment Sump Level and Dew Point Temperature

Procedures

Number Title Revision 1CST-1A-3010A Accumulator, Check Valve and Trip Valve Testing for Containment Cooler Inlet and Outlet Valves
11405-N-40 Auxiliary Coolant Component Cooling System P&ID Sheet 1 36
ER-AP-331-1003 RCS Leakage Monitoring and Action Plan
OP-PM-AFW-0004 Third Auxiliary Feedwater Pump Operability Verification
OP-ST-CCW-3002
AC-3A Component Cooling Water Pump In-service Test 35
OP-ST-CH-3008B Chemical and Volume Control System Boric Acid Pump
CH-4B Test 6
OP-ST-RC-3001 Reactor Coolant System (RCS) Leak Rate Test
OP-ST-RW-3002A Raw Water System Category A and B Valve Exercise Test
OP-ST-RW-3031
AC-10D Raw Water Pump Quarterly In-Service Test
OP-ST-SI-3021 Room 21 Safety Injection/Containment Spray Pumps and Valve Exercise In Service Test
OP-ST-SI-3022 Safety Injection/Containment Spray Pumps and Valve Exercise In

-Service Test, Room 22

OP-ST-VA-3001A Ventilating Air System Quarterly Category A Valve Exercise Test
OPST-ESF-00 22 S1-2 Automatic Load Sequencer Test
TS 2.4 Containment Cooling
249

Condition Reports

(CRs)

2016-05807 2015-04298 2016-05874

Work Orders

Number Title
572319 Task 01, Accumulator, Check Valve & Trip Valve Testing, "400 Series"

Work Orders

Number Title
574090 Task 01, FW

-54 Monthly Full Flow Operability Verification

576427 Task 01, EE

-91 A&B Verify Min Battery Voltage During Cranking of Dies el

578036 Task 01, Reactor Coolant System (RCS) Leak Rate Test Section 1EP6
Drill Evaluation

Miscellaneous

Documents Number Title Revision
Scenario:
Volume One FCS
EP drill off

-year exercise

EP-FC-1001 Addendum 3
Emergency Action Levels for FCS
EP-FC-1001 Radiological Emergency Response Plan FCS 0 RERP Radiological Emergency Response Plan

Procedures

Number Title Revision
EPIP-EOF-1 Activation of the Emergency Operations Facility

Condition Reports

(CRs)

2016-05807

Section 2RS1: Radiological Hazard Assessment and Exposure Controls

Audits and Self

-Assessments Number Title Date

NOSCPA-FC-14-17 Fort Calhoun Radiation Protection Performance Report October 16, 2014
NOSCPA-FC-15-11 Fort Calhoun Radiation Protection Performance Report October 5, 2015
NOSCPA-FC-16-03 Fort Calhoun Radiation Protection Performance Report April 1, 2016

Miscellaneous Documents

Number Title Date
Fort Calhoun Nuclear Safety Review Board Meeting Summary March 9, 2015
Fort Calhoun Station Nuclear Safety Review Board Meeting Summary August 21, 2015
NSTS Inventory Report January 4, 2016
SourceTrax Leak Test Record May 9, 2016
FC-1216 Annual Spent Fuel Pool Physical Inventory Log October 19, 2015
FC-RP-037-14 2013 Dry Active Waste Stream Off

-Site Sample Results April 8, 2014

L62402 2015 Dry Active Waste Stream Results April 13, 2015
RP-AA-800 SourceTrax Source Inventory July 2015
RP-AA-460, Att.
HRA Key Log July 20-21, 2016
RP-AA-460, Att.
LHRA Key Log July 20-21, 2016

Procedures

Number Title Revision
IC-CP-07-0006 Calibration of the Eberline Small Articles Monitor
SAM 12 5
RP-AA-10 Radiation Protection Process Description
RP-AA-100 Conduct of Radiation Protection Operations
RP-AA-300 Radiological Survey Program
RP-AA-376 Radiological Postings, Labeling, and Markings
RP-AA-403 Administration of the Radiation Work Permit Program
RP-AA-460 Controls for High and Locked High Radiation Areas
RP-AA-800 Control, Inventory, and Leak Testing of Radioactive Sources 7
RP-AA1008 Unescorted Access to and Conduct in Radiologically Controlled Areas Radiation Surveys Number Title Date 10620 Breathing Zone Sample for CH

-448 Repair May 13, 2016

Radiation Surveys Number Title Date M-20150419-19 Lower Reactor Cavity April 19, 2015
M-20150419-26 Lower Reactor Cavity April 19, 2015
M-20150706-2 'B' S/G Walkway, Elevation 1013' July 6, 2015
M-20160330-2 Room #5 L2AA
April 11, 2016
M-20150505-6
CH 188 Room #7
May 11, 2016
M-20160609-1 Room 31 June 9, 2016
Radiation Work Permits Number Title Revision 15-0618 Transfer Canal Blind Flange and LLRT
15-0651 Boric Acid Cleaning
15-0653 Rx Head Maintenance
0/1 16-0102 Operations Activities
16-0103 RP Activities
16-0207 Routine Decon Activities in HRAs/LHRAs
16-0306 CTMT Work @ Power with Added Controls
16-0326 RCP Seal Maintenance and Support Activities
16-0337
AC-236 Pipe Weld Repair

Condition Reports

(CR

-) 2015-05720 2015-05925 2015-05938 2015-06847 2015-06904 2015-07552 2015-08876 2015-08877 2015-08946 2015-10640 2015-11672 2015-11674

Section 2RS5: Radiation Monitoring Instrumentation

Audits and Self

-Assessments Number Title Date

NOSA-FCS-15-06 Radiation Protection Audit Report July 24, 2015
P3 2015(2)
FCS RMS System Health September 16, 2015 P4 2015(2) FCS RMS System Health June 26, 2016
P3 2016(2) FCS RMS System Health May 17, 2016
Audits and Self

-Assessments Number Title Date P3 2015(2)

FCS RMS System Health July 17, 2016
RA 2015-1442 Focused Area Pre

-NRC Inspection Self

-Assessment April 27, 2016

Miscellaneous Documents

Number Title Date
BX-3 Hopewell Calibration Irradiator Box February 19, 2015
FC-15-001 Evaluation of Instrument Response to Plant Radiol ogical Mix January 24, 2016
FC-14-002 Evaluation of Instrument Response to Plant Radiol ogical Mix May 28, 201 4
Portable Radiation Instrument Calibration Records Number Title Date 279
ASP-2E (Remball)
June 4, 2015 282
ASP-2E (Remball)
December 4, 2015 302
AMS-4 Continuous Air Monitor February 20, 2015
691 Hi-Vol Air Sampler March 9, 2015
291 Hi-Vol Air Sampler September 23, 201 4 2554
AMS-4 Continuous Air Monitor March 7, 2015 2554
AMS-4 Continuous Air Monitor June 6, 2015
6601-091 MGP Telepole March 25, 2015
6601-124 MGP Telepole March 25, 2015

Procedures

Number Title Revision
CH-CP-RA-0006 Calibration of Canberra Gamma Spectroscopy Detectors 13
CH-CP-RM-5300 Component Cooling Water Liquid Radiation Monitor, RM

-53, Primary Calibration

IC-CP-01-5300 Electronic & Secondary Calibration of Radiation Monitor, RM

-53 11

IC-CP-01-5500 Calibration of Eberline Model !M

-1A,

RM-65 6
IC-CP-01-6700 Calibration of Eberline Model PING

-1A,

RM-67 11

Procedures

Number Title Revision
IC-CP-02-0202 Calibration of the Eberline ASP

-2E with Remball

NRD 1
IC-CP-02-0205 Calibration of Ludlum Model 3030 Alpha/Beta Counter 3b
IC-CP-02-0210 Calibration of the Tennelec XLB
1a
IC-CP-02-0229 Calibration of MGP Telepole 8
IC-CP-02-0602 Calibration of Gooseneck LV Air Sampler
1a
IC-CP-02-0610 Calibration of Eberline AMS 3 Air Monitoring System 5
IC-CP-07-0006 Calibration of the Small Article Monitor SAM 12
IC-CP-07-0008 Calibration of the Eberline PM

-7 Portal Monitor

8a
IC-CP-07-0013 Calibration of the ARGOS

-5A/B PCM 1

IC-ST-RM-5500 Electronic And Secondary Calibration Of Radiation Monitor RM

-055 11

OP-ST-RM-0001 Area Radiation Monitor Checks
OP-ST-RM-0002 Process/Effluent Radiation Monitor & Effluent Flowrate Checks
RP-CP-07-0201 Calibration of Source Calibration Systems
RP-FC-700-AD-0201 Calibration of Source Calibration Systems
RP-AA-700-1239 Operation & Calibration of the Model SAM 12
TBD-IV.8 Area Monitoring Setpoints
TBD-IV.7 Process Monitor Setpoints 229
Radiation Monitoring System Calibration Records Number Title Date
WO-446910 Process Radiation Monitor RM

-53 June 13, 2013

WO-475850 Process Radiation Monitor RM

-65 January 29, 2014

WO-485608 Process Radiation Monitor RM

-64 April 14, 2014

WO-494600 Process Radiation Monitor RM

-67 July 15, 2014

WO-546538 Process Radiation Monitor RM

-67 July 13, 2014

WO-588704 Process Radiation Monitor RM

-63 July 16, 2016

WO-671143 Process Radiation Monitor RM

-65 July 15, 2016

Stationary Radiation Instrument Calibration Records Number Title Date 110 Argos 5B January 6, 2016
111 Argos 5B December 10, 2015 133 Count Room SAM

-12 December 2, 2015 134 Count Room SAM

-12 August 27, 2015

2 Radwaste PM

-7 March 12, 2015

2 Radwaste PM

-7 March 10, 2016

243 Tennelec XLB
October 21, 2015
2792 Ludlum Model 3030 Alpha

-Beta Counter March 8, 2016

Admin FS2 Calibration Admin Bldg. FastScan2
WBC System November 3, 2015
Detector 1
Calibration of Canberra Gamma Spectroscopy Detectors December 15 , 2015 Plant AC2 Calibration AccuScan2 WBC System February 25, 2016
Plant FS 2 Calibration Admin Bldg.
FastScan2
WBC System February 25, 2016

Condition Reports

(CR

-) 2014-11553 2014-14872 2014-15152 2015-04956 2015-05423 2015-09208 2015-13987 2016-00585 2016-02369 2015-13757 2015-00512 2015-07137

Section 2RS6: Radioactive Gaseous and Liquid Effluent Treatment

Audits and Self

-Assessments Number Title Date

RA 2015-1442 Focused Area Self

-Assessment June 17, 2016

Effluent Monitor Calibration Records
W/O Number Title Date
Electronic and Secondary Calibration of Radiation Monitor RM

-054A March 1, 2016

Electronic and Secondary Calibration of Radiation Monitor RM

-054B March 1, 2016

Steam Generator "A" Blowdown Liquid Radiation Monitor, RM

-054A, Primary Calibration January 22, 2016

Effluent Monitor Calibration Records
W/O Number Title Date
Steam Generator "B" Blowdown Liquid Radiation Monitor, RM

-054B, Primary Calibration January 22, 2016

000534700 Calibration of Auxiliary Building Exhaust Stack Total Ventilation Flow, Loop
F-758 April 28, 2016
00485608 Electronic and Secondary Calibration of Radiation Monitor RM

-064 April 9, 2014

00503580 Electronic and Secondary Calibration of Radiation Monitor RM

-055 (Liquid Waste Monitor)

June 13, 2014
00510640 Electronic and Secondary Calibration of Radiation Monitor RM

-052 (Containment/Vent Stack Monitor)

November 1, 2014
00518572 Calibration of Post Accident Radiation Monitor RM

-063 March 13, 2015

00532157 Electronic and Secondary Calibration of Radiation Monitor RM

-062 (Aux Bldg Vent Stack)

April 6, 2015
00538166 Electronic and Secondary Calibration of Radiation Monitor RM

-064 June 19, 2015

00545103 Electronic and Secondary Calibration of Radiation Monitor RM

-057 (Condenser Off

-Gas Monitor)

October 8, 2015
00554641 Electronic and Secondary Calibration of Radiation Monitor RM

-055 (Liquid Waste Effluent Monitor)

February 19, 2016
00560218 Electronic and Secondary Calibration of Radiation Monitor RM

-052 (Containment/Vent Stack Monitor)

May 17, 2016
00561162 Calibration of Laboratory and Radioactive Waste Processing Building Exhaust Stack Total Ventilation Flow, Loop F

-6699 May 26, 2016

00566733 Electronic and Secondary Calibration of Radiation Monitor RM

-062 (Aux Bldg Vent Stack)

October 6, 2015
In-Place Filter Testing and Carbon Testing Records
W/O Number Title Date
00470593 Containment HEPA Filter Banks VA

-5A/VA-5B Refueling Inspection May 23, 2015

00525582 Freon Test of Safety Injection Pump Room Charcoal Filter Absorbers
VA-26A/26B November 23, 2015
00540507 Freon Test of Spent Fuel Pool Area Charcoal Filter VA

-66 October 26, 2015

00543969 Safety Injection Pump Room Charcoal Filter VA

-26A/26B Elemental Iodine Removal Efficiency Test November 24, 2015

In-Place Filter Testing and Carbon Testing Records
W/O Number Title Date
00554642 Verification of Spent Fuel Pool Area Filter unit VA

-66 Flow December 4, 2015

Miscellaneous Documents

Number Title Date 1 st
QTR 2016 Radiation Monitoring System Health Report
2014 Annual Radiological Effluent Release Report
2014 Interlaboratory Comparison
2015 Annual Radiological Effluent Release Report May 1, 2016
2015 Interlaboratory Comparison
2006 Engineering Change: Replacement of Radiation Monitor Components December 22, 2015 TD V964.0010
Installation, Operating and Maintenance Manual for Vortek Electronic Airflow Transmitter November 16, 1995

Procedures

Number Title Revision
CH-AD-0055 Special Radiological Liquid Release Permit and Summary 4
CH-ODCM-0001 Off-Site Dose Calculation Manual (ODCM)
CH-SMP-RE-0013 Auxiliary Building Exhaust Stack Sampling
CH-SMP-RE-0018 Laboratory And Radioactive Waste Processing Building Exhaust Stack Sampling
CH-SMP-RE-0019 Auxiliary Building Tritium Sampling Using Either RM

-062 or

RM-052 5
CH-ST-RM-5400 Steam Generator "A" Blowdown Liquid Radiation Monitor, RM

-054A, Primary Calibration 10

CH-ST-RM-5401 Steam Generator "B" Blowdown Liquid Radiation Monitor, RM

-054B, Primary Calibration

CH-ST-VA-0001 Auxiliary Building Exhaust Stack Sampling and Analysis 14
CH-ST-VA-0002 Laboratory and Radioactive Waste Processing Building Exhaust Stack Sampling and Analysis
IC-ST-RM-5200 Electronic and Secondary Calibration of Radiation Monitor RM

-052 27

Procedures

Number Title Revision
IC-ST-RM-5400 Electronic and Secondary Calibration of Radiation Monitor RM

-054A 20

IC-ST-RM-5401 Electronic and Secondary Calibration of Radiation Monitor RM

-054B 16

IC-ST-RM-5500 Electronic and Secondary Calibration of Radiation Monitor RM

-055 11

IC-ST-RM-5700 Electronic and Secondary Calibration of Radiation Monitor RM

-057 25

IC-ST-RM-6200 Electronic and Secondary Calibration of Radiation Monitor RM

-062 20

IC-ST-RM-6400 Electronic and Secondary Calibration of Radiation Monitor RM

-064 9

IC-ST-VA-0026 Calibration of Auxiliary Building Exhaust Stack Total Ventilation Flow, Loop F

-758 14

IC-ST-VA-0038 Calibration of Laboratory and Radioactive Waste Processing Building Exhaust Stack Total Ventilation Flow, Loop F

-6699 5

SE-ST-VA-0004 Freon Test of Safety Injection Pump Room Charcoal Filter Absorbers
VA-26A/26B 7
SE-ST-VA-0005 Safety Injection Pump Room Charcoal Filter VA

-26A/26B Elemental Iodine Removal Efficiency Test

SE-ST-VA-0009 Freon Test of Spent Fuel Pool Area Charcoal Filter
VA-66 10
TDB-IV.7 Technical Data Book: Process Monitor Set Points
29
Radioactive Effluent Release Permits and Summaries Release Number Title Date
2014002 Waste Gas Decay Tank Release Permit (WGDT

-D) April 30, 2014

2015006 Condenser Air Ejector Release Summary July 1, 2015
2015007 Waste Gas Decay Tank Release Permit (WGDT

-B) June 6, 2015

2015013 Special Radiological Liquid Release Permit April 30, 2015
2015018 Auxiliary Building Exhaust Stack Release Summary May 5, 2015
2015018 Special Radiological Liquid Release Permit May 5 2015
2015023 Special Radiological Liquid Release Permit May 7, 2015
2015030 Auxiliary Building Exhaust Stack Release Summary July 28, 2015
Radioactive Effluent Release Permits and Summaries Release Number Title Date
2015040 Steam Generator Batch Release Permit May 9, 2015
2016006 Containment Release Permit February 11, 2016
2016019 Waste Liquid Tank Release Permit (MT

-A) March 8, 2016

2016029 Auxiliary Building Exhaust Stack Release Summary July 19, 2016
2016029 Laboratory and Radioactive Waste Processing Building Exhaust Stack Release Summary July 19, 2016
2016031 Containment Release Permit July 21, 2016
2016040 Steam Generator Release Summary (SG

-B) May 19, 2016

2016082 Waste Liquid Tank Release Permit (MT

-A) July 19, 2016

Condition Reports

(CR

-) 2014-11553 2014-12842 2014-12842 2014-12866 2014-12928 2014-14251 2015-00858 2015-10850 2015-11564 2015-12459 2015-13374 2016-00237 2016-00401 2016-00835 2016-00860 2016-01455 2016-04552 2016-05774

Section 2RS8: Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage, and

Transportation Audits and Self

-Assessments Number Title Date

NOSA-FCS-16-04 Chemistry, Radwaste, Effluent and Environmental Monitoring Audit Report July 15, 2016
NOSCPA-FC-16-03 Fort Calhoun Radiation Protection Performance Report April 1, 2016
RA 2015-1442 Focused Area Self

-Assessment April 27, 2016

Miscellaneous Documents

Number Title Date
2015 Waste Stream Results Dry Active Waste January 20, 2015
Waste Stream Nuclide Distribution Report June 19, 2016
Quarterly Radwaste Storage Facility/Waste Liner Container Integrity Inspection
2014-2016

Miscellaneous Documents

Number Title Date
FC-RP-037-14 2013 Dry Active Waste Stream Off

-Site Sample Results April 8, 2014

Procedures

Number Title Revision/Date
QCP-235 Radioactive Material Shipments and Preparation for Shipment Inspections (Superseded on March 3, 2016)
RE-ST-RX-0004 Boral Sample Coupon Retrieval and Testing June 27, 2013
RP-AA-14 Radioactive Material Control Program Description
RP-AA-500 Radioactive Material (RAM) Control
RP-AA-500-1001 Requirements for Radioactive Materials Stored Outdoors 5
RP-AA-600 Radioactive Material/Waste Shipments
RP-AA-600-1001 Exclusive Use and Emergency Response Information
RP-AA-600-1004 Radioactive Waste Shipments to Energy Solutions' Clive Utah Disposal Site Containerized Waste Facility
RP-AA-600-1005 Radioactive Material and Non

-Disposal Site Waste Shipments 18

RP-AA-600-1008 Radioactive Waste Shipments to Waste Control Specialists Disposal Facility
RP-AA-600-1010 Use and Operation of WMG Software for Creating Containers, Samples, Waste Streams and Waste Types 2
RP-AA-601 Surveying Radioactive Material Shipments
RP-AA-602 Packaging of Radioactive Material Shipments
RP-AA-603 Inspection and Loading of Radioactive Material Shipments 10
RP-AA-605 10
CFR 61 Program
RP-AA-631 Dry Radioactive Waste Generation and Reduction
RW-202 Collection of Dry Active Waste
RW-AA-10 Radwaste Process Description
RW-AA-100 Process Control Program for Radioactive Wastes

Procedures

Number Title Revision/Date
RW-AA-102 Radwaste Storage Facility/DAW Waste Container Inspections
RW-AA-1000 Radwaste Monthly Report Guideline
RW-AA-104 Radwaste Storage Facility/Waste Container Inspections Radioactive Materials Shipments Number Title Date 09-14
UN 3321, Fissile-Excepted, Radioactive Material,
LSA-II - Resin June 17, 2009
14-16 UN2910, Fissile

-Excepted, Radioactive Material, Limited Quantity November 13, 2014 15-12 UN2912, Fissile-Excepted, Radioactive Material, LSA

-I - DAW April 21, 2015

15-15 UN2912, Fissile

-Excepted, Radioactive Material, LSA

-I - DAW May 1, 2015

15-34 UN3321, Fissile

-Excepted, Radioactive Material, LSA

-II June 1, 2015

Surveys Number Title Date M-20160621-3 Owner Control Old Warehouse Monthly July 21, 2016
M-20160531-1 Owner Controlled RA/RMA/Old Warehouse Survey May 31, 2016
M-20160710-1 Room 502 July 10, 2016

Condition Reports

(CRs)

2016-05384 2016-05385 2015-00364 2015-05913 2016-03088 2015-01213 2015-12016 2015-04731 2015-04727 2016-03846 2016-04303 2015-14166 2015-09823 2014-13098 2014-11800
Section 4OA1
Performance Indicator Verification

Miscellaneous Documents

Number Title Revision/Date
Control Room Logs

Miscellaneous Documents

Number Title Revision/Date
Maintenance Rule Performance Criteria for Raw Water System
Mitigating System Performance Index Basis Document
MSPI Derivation Reports for Heat Removal System, Cooling Water System, and High Pressure Injection System July 1 through June 30, 2016 99-02 NEI, Regulatory Assessment Performance Indicator Guidelines

Procedures

Number Title Revision
LS-AA-2001 Collecting and Reporting of NRC Performance Indicator Data 14
LS-AA-2200 Mitigating System Performance Index Data Acquisition and Reporting 5

Condition Reports

(CRs)

2016-05807
Section 4OA2
Problem Identification and Resolution

Miscellaneous Documents

Number Title
Safety Injection Tank Boron Concentration Adverse Condition Monitoring Plan Safety Injection Tank Boron Concentration Trending Plots
2015-10181 Apparent Cause Evaluation Report

Procedures

Number Title Revision
CH-ST-SI-0002 Safety Injection Tank Boron Sampling and Analysis

Condition Reports

(CRs)

2015-10181 2015-12964 2016-05807
Section 4OA3
Follow-up of Events and Notices of Enforcement Discretion

Miscellaneous Documents

Number Title Revision/Date Control Room Logs
2.6 Technical Specification, Containment System Ansi/Ans-3.4 Medical Certification And Monitoring Of Personnel Requiring Operator Licenses For Nuclear Power Plants
1996

Procedures

Number Title Revision
AOP-1 Acts of Nature
AOP-12 Loss of Containment Integrity
EP-FC-1001 Emergency Action Levels for Fort Calhoun Station, Addendum 3
EP-FC-1001 Radiological Emerg enc y Response Plan for Fort Calhoun Station 0

Condition Reports

(CRs)

2013-21774 2014-00376 2014-00379 2014-05108 2014-05371 2014-05374 2014-05375 2014-05377 2014-14242 2015-03619 2015-10600 2016-05807 2016-07037 2016-07038 2016-07133 2016-07134 2016-07135 2016-07137 2016-07138 2016-07140 2016-07147 2016-07151 2016-07167
Section 4OA5
Other Activities

Procedures

Number Title Date
Check-In Self-Assessment, Self

-Assessment of Design and Licensing Basis Configuration Control (CR

2013-05570-064) June 1, 2016
Nuclear Oversight Audit Report, Engineering Design Control August 26, 2015
NED-13-155 DEN Site Vice President Memo, Restriction of Individuals Preparing/Reviewing 10
CFR 50.59 Product May 7, 2013
CFR 50.59 Lessons Learned Briefing September 13, 2013

Condition Reports

(CRs)

2015-09132 2016-03876 2016-04839
Attachment 2
The following items are requested for the Occupational/Public Radiation Safety Inspection at Fort Calhoun Station July 18 - 22, 2016 Integrated Report 2016003
Inspection areas are listed in the attachments below.
Please provide the requested information on or before June 27, 2016

.

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.
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 Louis Carson at (817) 817-200-1221 or Louis.Carson@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:
May 18, 2015
A. List of contacts and telephone numbers for the Radiation Protection Organization Staff and Technicians
B. Applicable organization charts
C. Audits, self

-assessments, and LERs written since date of last inspection

, related to this inspection area

D. Procedure indexes for the radiation protection procedures
E. Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures may be requested by number after the inspector review

s the procedure indexes.

1. Radiation Protection Program Description
2. Radiation Protection Conduct of Operations
3. Personnel Dosimetry Program
4. Posting of Radiological Areas
5. High Radiation Area Controls
6. RCA Access Controls and Radworker Instructions
7. Conduct of Radiological Surveys 8. Radioactive Source Inventory and Control
9. Declared Pregnant Worker Program
F. List of corrective action documents (including corporate and sub

-tiered systems) since date of last inspection

1. Initiated by the radiation protection organization
2. Assigned to the radiation protection organization
NOTE: The lists should indicate the significance level of each issue and the search criteria used.
Please provide in document formats which are "searchable" so that the inspector can perform word searches.
If not covered above, a summary of corrective action documents since date of last inspection involving unmonitored releases, unplanned releases, or releases in which any dose limit or administrative dose limit was exceeded (for Public Radiation Safety Performance Indicator verification in accordance with IP 71151)
G. 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.)
H. List of active radiation work permits
I. Radioactive source inventory list
1. All radioactive sources that are required to be leak tested
2. All radioactive sources that meet the 10 CFR Part 20, Appendix E, Category 2

, and above threshold.

Please indicate the radioisotope, initial and current activity (w/assay date), and storage location for each applicable source.
J. The last two leak test results for the radioactive sources inventoried and required to be leak tested.
If applicable, specifically provide a list of all radioactive source(s) that have failed its leak test within the last two years
K. A current listing of any non

-fuel items stored within your pools, and if available, their appropriate dose rates (Contact / @ 30cm)

L. Computer printout of radiological controlled area entries greater than 100 millirems since the previous inspection to the current inspection entrance date.
The printout 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 setpoint used during the entry (for Occupational Radiation Safety Performance Indicator verification in accordance with IP 71151)

.

5. Radiation Monitoring Instrumentation (71124.05)
Date of Last Inspection:
September 15, 201
A. List of contacts and telephone numbers for the following areas:
1. Effluent monitor calibration
2. Radiation protection instrument calibration
3. Installed instrument calibrations
4. Count room and Laboratory instrument calibrations
B. Applicable organization charts
C. Copies of audits, self

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

, related to:

1. Area radiation monitors, continuous air monitors, criticality monitors, portable survey instruments, electronic dosimeters, teledosimetry, personnel contamination monitors, or whole body counters
2. Installed radiation monitors
D. Procedure index for:
1. Calibration, use and operation of continuous air monitors, criticality monitors, portable survey instruments, temporary area radiation monitors, electronic dosimeters, teledosimetry, personnel contamination monitors, and whole body counters
2. Calibration of installed radiation monitors
E. Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
1. Calibration of portable radiation detection instruments (for portable ion chambers)
2. Whole body counter calibration
3. Laboratory instrumentation quality control
F. A summary list of corrective action documents (including corporate and sub

-tiered systems) written since date of last inspection, related to the following programs:

1. Area radiation monitors, continuous air monitors, criticality monitors, portable survey instruments, electronic dosimeters, teledosimetry, personnel contamination monitors, whole body counters
2. Installed radiation monitors
3. Effluent radiation monitors
4. Count room radiation instruments
NOTE:
The lists should indicate the significance level of each issue and the search criteria used.
Please provide in document formats which are "searchable" so that the inspector can perform word searches.
G. Offsite dose calculation manual, technical requirements manual, or licensee controlled specifications which lists the effluent monitors and calibration requirements
H. Current calibration data for the whole body counter's
I. Primary to secondary source calibration correlation for effluent monitors
J. A list of the point of discharge effluent monitors with the two most recent calibration dates and the work order numbers associated with the calibrations.
K. Radiation Monitoring System health report for the previous 12 months
6. Radioactive Gaseous and Liquid Effluent Treatment (71124.06)
Date of Last Inspection:
September 15, 2014
A. List of contacts and telephone numbers for the following areas:
1. Radiological effluent control
2. Engineered safety feature air cleaning systems
B. Applicable organization charts
C. Audits, self

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

1.
Radioactive effluents
2.
Engineered Safety Feature Air cleaning systems
D. Procedure indexes for the following areas
1.
Radioactive effluents
2.
Engineered Safety Feature Air cleaning systems
E. Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
1. Sampling of radioactive effluents
2. Sample analysis
3. Generating radioactive effluent release permits
4. Laboratory instrumentation quality control
5. In-place testing of HEPA filters and charcoal absorbers
6. New or applicable procedures for effluent programs (e.g., including ground water monitoring programs)
F. List of corrective action documents (including corporate and sub

-tiered systems) written since date of last inspection, associated with:

1. Radioactive effluents
2. Effluent radiation monitors
3. Engineered Safety Feature Air cleaning systems
NOTE:
The lists should indicate the significance level of each issue and the search criteria used.
Please provide in document formats which are "searchable" so that the inspector can perform word searches.
G. 2014 and 2015
Annual Radioactive Effluent Release Report or the two most recent reports
H. Current Copy of the Offsite Dose Calculation Manual
I. Copy of the 2014 and 2015

inter-laboratory comparison results for laboratory quality control performance of effluent sample analysis or the two most recent results

J. Effluent sampling schedule for the week of the inspection
K. New entries into 10
CFR 50.75(g) files since date of last inspection
L. Operations department

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

M. Listing or log of liquid and gaseous release permits since date of last inspection
N. 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 absorbers) and laboratory testing (of charcoal efficiency) and the work order numbers associated with the surveillances

O. 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 November 2011.
If applicable, please provide the relative Special Report and condition report(s).
P. A list of all radiation monitors that are considered §
50.65/Maintenance Rule equipment.
Q. A list of all significant changes made to the Gaseous and Liquid Effluent Process Monitoring System since the last inspection.
If applicable, please provide the corresponding UFSAR section in which this change was documented.
R.
A list of any occurrences in which a non

-radioactive system was contaminated by a radioactive system.

Please include any relative condition report(s).
8. Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage, and Transportation (71124.08)
Date of Last Inspection:
September 15, 2014
A. List of contacts and telephone numbers for the following areas:
1. Solid Radioactive waste processing
2. Transportation of radioactive material/waste
B. Applicable organization charts (and list of personnel involved in solid radwaste processing, transferring, and transportation of radioactive waste/materials)
C. Copies of audits, department self

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

1. Solid radioactive waste management
2. Radioactive material/waste transportation program
D. Procedure index for the following areas:
1. Solid radioactive waste management
2. Radioactive material/waste transportation
E. Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
1. Process control program
2. Solid and liquid radioactive waste processing
3. Radioactive material/waste shipping
4. Methodology used for waste concentration averaging, if applicable
5. Waste stream sampling and analysis
F. A summary list of corrective action documents (including corporate and sub

-tiered systems) written since date of last inspection related to:

1. Solid radioactive waste
2. Transportation of radioactive material/waste
NOTE:
The lists should indicate the significance level of each issue and the search criteria used.
Please provide in document formats which are "searchable" so that the inspector can perform word searches.
G. Copies of training lesson plans for 49CFR172 subpart H, for radwaste processing, packaging, and shipping
H. A summary of radioactive material and radioactive waste shipments made from date of last inspection to present
I. Waste stream sample analyses results and resulting scaling factors for 2014 and 2015 , or the two most recent results
J. Waste classification reports if performed by vendors (such as for irradiated hardware)
K. A listing of all onsite radwaste storage facilities.
Please include a summary or listing of the items stored in each facility, including the total amount of radioactivity and the highest general area dose rate.
Although it is not necessary to compile the following information, the inspector will also review
L. Training and qualifications records of personnel responsible for the conduct of radioactive waste processing, package preparation, and shipping
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