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=Text=
=Text=
{{#Wiki_filter:ber 21, 2015
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ber 21, 2015


==SUBJECT:==
==SUBJECT:==
NRC INSPECTION REPORT NO. 05000302/201500 9, DUKE ENERGY FLORIDA, INC., CRYSTAL RIVER UNIT 3, CRYSTAL RIVER, FLORIDA
NRC INSPECTION REPORT NO. 05000302/2015009, DUKE ENERGY FLORIDA, INC., CRYSTAL RIVER UNIT 3, CRYSTAL RIVER, FLORIDA


==Dear Mr. Hobbs:==
==Dear Mr. Hobbs:==
On September 30, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its quarterly inspection under Inspection Manual Chapter 2561, "Decommissioning Power Reactor Inspection Program," at the permanently shut down Crystal River Nuclear Plant Unit 3 (CR-3). On-site inspections were performed on August 25-2 7, 2015. In-office reviews of information supplied by Duke Energy Florida, Inc. were also performed during the inspection period. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Phyllis Dixon, Decommissioning Technical Support Manager, and other members of the CR-3 staff on October 5, 2015, and are described in the enclosed report.
On September 30, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its quarterly inspection under Inspection Manual Chapter 2561, Decommissioning Power Reactor Inspection Program," at the permanently shut down Crystal River Nuclear Plant Unit 3 (CR-3). On-site inspections were performed on August 25-27, 2015. In-office reviews of information supplied by Duke Energy Florida, Inc. were also performed during the inspection period. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Phyllis Dixon, Decommissioning Technical Support Manager, and other members of the CR-3 staff on October 5, 2015, and are described in the enclosed report. No findings of safety significance were identified.


No findings of safety significance were identified.
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure(s), and your response, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC document system (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.


In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure(s), and your response, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC document system (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Radioactive Waste; Decommissioning of Nuclear Facilities; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Steve Hammann, at 610-337-5399, if you have any questions regarding this matter.
 
Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Radioactive Waste; Decommissioning of Nuclear Facilities; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also
 
obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays).
 
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 No reply to this letter is required. Please contact Steve Hammann, at 610-337-5399, if you have any questions regarding this matter.


Sincerely,
Sincerely,
/RA/ Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure:
/RA/
Inspection Report 05000302/201500 9 cc w/encl:
Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure: Inspection Report 05000302/2015009 cc w/encl: Distribution via ListServ
Distribution via ListServ


=EXECUTIVE SUMMARY=
=EXECUTIVE SUMMARY=
Duke Energy  
Duke Energy


Crystal River Nuclear Plant NRC Inspection Report No. 05000302/201500 9  An announced quarterly inspection was completed at CR
Crystal River Nuclear Plant NRC Inspection Report No. 05000302/2015009 An announced quarterly inspection was completed at CR-3 on September 30, 2015. On-site inspections were conducted on August 25-27, 2015. In-office reviews of information supplied by Duke Energy were also performed during the inspection period. The inspection included a review of site operations, management oversight, site radiological programs, maintenance and surveillance, and decommissioning performance. The inspection consisted of observations by the inspector, interviews with Duke Energy personnel, a review of procedures and records, and plant walk-downs. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561,
-3 on September 30, 2015. O n-site inspection s were conducted on August 25-27 , 2015. In-office reviews of information supplied by Duke Energy were also performed during the inspection period. The inspection included a review of site operations
Decommissioning Power Reactor Inspection Program."
, management oversight, site radiological programs, maintenance and surveillance, and decommissioning performance.
 
The inspection consisted of observations by the inspector, interviews with Duke Energy personnel, a review of procedures and records, and plant walk-downs. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561,  
"Decommissioning Power Reactor Inspection Program."


Based on the results of this inspection, no findings of safety significance were identified.
Based on the results of this inspection, no findings of safety significance were identified.


3  Inspection Report No. 05000302/201500 9 G:\WordDocs\Mailed\Insp Letter
ii    Inspection Report No. 05000302/2015009 G:\WordDocs\Mailed\Insp Letter\LDPR-72.201500910212015.docx
\LDPR-72.201500910212015.docx


=REPORT DETAILS=
=REPORT DETAILS=


1.0 Background On February 20, 2013, Duke Energy sent a letter  
1.0   Background On February 20, 2013, Duke Energy sent a letter [Agency Documentation and Management System (ADAMS) Accession Number: ML13056A005] to the NRC certifying the permanent cessation of activities and certifying that the fuel had been permanently removed from the reactor. This met the requirements of 10 Code of Federal Regulations (CFR) 50.82(a)(1)(i) and 50.82(a)(1)(ii). As of the end of this reporting period, Crystal River Unit 3 (CR-3) has moved from the Post Operation Transitional Phase of decommissioning to the SAFSTOR phase of decommissioning as described in IMC 2561.
[Agency Documentation and Management System (ADAMS) Accession Number
: ML13056A005]
to the NRC certifying the permanent cessation of activities and certifying that the fuel had been permanently removed from the reactor. This met the requirements of 10 Code of Federal Regulations (CFR) 50.82(a)(1)(i) and 50.82(a)(1)(ii). As of the end of th is reporting period, Crystal River Unit 3 (CR-3) has moved from the "Post Operation Transitional Phase" of decommissioning to the SAFSTOR phase of decommissioning as described in IMC 2561.


2.0 Post Operation Transition Phase Performance and Status Review
2.0   Post Operation Transition Phase Performance and Status Review


====a. Inspection Scope====
====a. Inspection Scope====
(Inspection Procedures (IPs) 62801 , 71801, 83750, 8 6750)
(Inspection Procedures (IPs) 62801, 71801, 83750, 86750)
The inspector performed a n on-site inspection the week of August 2 5-2 7, 2015. In-office reviews of information supplied by Duke Energy were also performed during the inspection period.
The inspector performed an on-site inspection the week of August 25-27, 2015. In-office reviews of information supplied by Duke Energy were also performed during the inspection period. The inspection consisted of observations by the inspector, interviews with Duke Energy personnel, a review of procedures and records, and plant walk-downs.


The inspection consisted of observations by the inspector, interviews with Duke Energy personnel, a review of procedures and records, and plant walk
The inspector reviewed activities and documentation associated with the occupational exposure and radioactive waste management to determine the effectiveness of site radiological programs. The inspector accompanied a CR-3 radiation protection (RP)technician during a plant walk-down which included; checking postings, general area surveys, air sample collection and analysis. The inspector also toured the instrument calibration lab and reviewed the setup of the calibrator and reviewed calibration procedures. The inspector observed work activities associated with the processing, packaging, surveying, and storage of radwaste and reviewed the work package for the most recent shipment of radwaste to verify compliance with the regulations. The inspector reviewed year-to-date dose totals, radiation work permits, and As Low As Reasonably Achievable work plans to verify radiation work activities were pre-planned effectively to limit worker exposure.
-downs.


The inspector reviewed activities and documentation associated with the occupational exposure and radioactive waste management to determine the effectiveness of site radiological programs. The inspector accompanied a CR
The inspector reviewed the completed work package and related procedures completed for the quarterly preventative maintenance of the fuel handling crane to verify that maintenance was being performed within the established frequencies and that the equipment was being properly maintained. The inspector also met with CR-3 maintenance supervisors and discussed staffing levels, how routine maintenance and emergent work is requested, prioritized, and scheduled, and reviewed the current maintenance workload. The inspector reviewed the backlog of maintenance work to assess the age and prioritization of the items.
-3 radiation protection (RP) technician during a plant walk
-down which included; checking postings, general area surveys, air sample collection and analysis. The inspector also toured the instrument calibration lab and reviewed the setup of the calibrator and reviewed calibration procedures. The inspector observed work activities associated with the processing, packaging, surveying, and storage of radwaste and reviewed the work package for the most recent shipment of radwaste to verify compliance with the regulations. The inspector reviewed y ear-to-date dose totals , radiation work permits , and As Low As Reasonably Achievable work plans to verify radiation work activities were pre
-planned effectively to limit worker exposure.


The inspector reviewed the completed work package and related procedures completed for the quarterly preventative maintenance of the fuel handling crane to verify that maintenance was being performed within the established frequencies and that the equipment was being properly maintained. The inspector also met with CR
Inspection Report No. 05000302/2015009 G:\WordDocs\Mailed\Insp Letter\LDPR-72.201500910212015.docx
-3 maintenance supervisors and discussed staffing levels, how routine maintenance and emergent work is requested, prioritized, and scheduled, and reviewed the current maintenance workload. The inspector reviewed the backlog of maintenance work to assess the age and prioritization of the items.


Inspection Report No. 05000302/2015009 G:\WordDocs\Mailed\Insp Letter
The inspector observed CR-3 and Areva, Inc. personnel performing visual inspections of spent fuel assemblies in order to assess the material condition of the spent fuel assemblies. The visual inspections are in preparation for the CR-3 campaign to move all fuel assemblies from the spent fuel pool and into dry cask storage. The inspector reviewed the equipment setup, RP coverage of the project, and evaluated CR-3s adherence to procedures.
\LDPR-72.201500910212015.docx The inspector observed CR-3 and Areva, Inc. personnel performing visual inspections of spent fuel assemblies in order to assess the material condition of the spent fuel assemblies. The visual inspections are in preparation for the CR-3 campaign to move all fuel assemblies from the spent fuel pool and into dry cask storage. The inspector reviewed the equipment setup , RP coverage of the project, and evaluated CR
-3's adherence to procedures.


====b. Observations and Findings====
====b. Observations and Findings====
The inspector attended pre
The inspector attended pre-job briefings and determined that briefings were thorough and identified the significant potential hazards for the activities to be performed. The inspector determined that survey records were clear and complete and RP staff effectively controlled work activities. The inspector noted most routine surveys, instrument calibrations and daily source checks of instruments are performed on back shift. The inspector also noted that most radwaste has been shipped off-site and several large legacy radwaste items are scheduled to be shipped within the next year.
-job briefings and determined that briefings were thorough and identified the significant potential hazards for the activities to be performed. The inspector determined that survey records were clear and complete and RP staff effectively controlled work activities.


The inspector noted most routine surveys, instrument calibrations and daily source checks of instruments are performed on back shift. The inspector also noted that most radwaste has been shipped off
The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the technical specifications requirements and established procedures. The inspector determined that approximately 20% of maintenance work is preventative maintenance and the rest is emergent work. The inspector also determined that approximately 90% of the maintenance workload is non-complex and does not require a work order.
-site and several large legacy radwaste items are scheduled to be shipped within the next year.
 
The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the technical specifications requirements and established procedures.
 
The inspector determined that approximately 20% of maintenance work is preventative maintenance and the rest is emergent work.
 
The inspector also determined that approximately 90% of the maintenance workload is non
-complex and does not require a work order.


The inspector noted that the visual inspection of fuel assemblies was being performed using multiple cameras and that all four sides, top, and bottom are viewed and that all visuals are recorded. The inspector verified that a second independent individual views the monitors to verify results and all deformations of fuel assemblies are noted. The inspector noted that CR-3 plans to further test the fuel assemblies with deformations to ensure they will be able to be loaded into dry casks.
The inspector noted that the visual inspection of fuel assemblies was being performed using multiple cameras and that all four sides, top, and bottom are viewed and that all visuals are recorded. The inspector verified that a second independent individual views the monitors to verify results and all deformations of fuel assemblies are noted. The inspector noted that CR-3 plans to further test the fuel assemblies with deformations to ensure they will be able to be loaded into dry casks.
Line 106: Line 75:


=====Exit Meeting Summary=====
=====Exit Meeting Summary=====
On October 5, 2015, the inspector presented the inspection results, via teleconference, to Phyllis Dixon, Decommissioning Technical Support Manager, and other members of Duke Energys staff. The inspectors confirmed that proprietary information was not removed from the site.


On October 5, 2015 , the inspector presented the inspection results, via teleconference, to Phyllis Dixon, Decommissioning Technical Support Manager, and other members of Duke Energy's staff. The inspectors confirmed that proprietary information was not removed from the site
Inspection Report No. 05000302/2015009 G:\WordDocs\Mailed\Insp Letter\LDPR-72.201500910212015.docx PARTIAL LIST OF PERSONS CONTACTED Licensee K. Ankrum, Finance B. Akins, Radiation Protection and Chemistry Manager J. Campbell, RP Tech P. Dixon, Decommissioning Technical Support Manager J. Gaines, Sr. HR Consultant K. Hirsch, Lead Scientist T. Hobbs, Decommissioning General Manager R. Macko, Sr. Scientist P. Rose, Licensing I. Wilson, General Manager Decommissioning (Acting)
.
K. Shelton, RP Supervisor J. Stoney, Radwaste Tech D. Sumners, RP Tech M. Van Sicklen, Licensing H. Wojtasinski, Maintenance Supervisor ITEMS OPEN, CLOSED, AND DISCUSSED None LIST OF  
PARTIAL LIST OF PERSONS CONTACTED Licensee K. Ankrum, Finance B. Akins, Radiation Protection and Chemistry Manager J. Campbell, RP Tech P. Dixon , Decommissioning Technical Support Manager J. Gaines, Sr. HR Consultant K. Hirsch, Lead Scientist T. Hobbs , Decommissioning General Manager R. Macko, Sr. Scientist P. Rose, Licensing I. Wilson, General Manager Decommissioning (Acting)
K. Shelton, RP Supervisor J. Stoney, Radwaste Tech D. Sumners, RP Tech M. Van Sicklen, Licensing H. Wojtasinski, Maintenance Supervisor ITEMS OPEN, CLOSED, AND DISCUSSED
 
None LIST OF  


=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=
Line 120: Line 86:
2014-CR3-REW-01 Audit Report
2014-CR3-REW-01 Audit Report
2015-CR3-QA-01 Audit Report
2015-CR3-QA-01 Audit Report
RP Self Assessment 734454
RP Self Assessment 734454-11, Respiratory Protection, Rad Material Storage, Rad Posting &
-11, Respiratory Protection, Rad Material Storage, Rad Posting &
Labeling, April 2015
Labeling, April 2015
Procedures
Procedures
AD-RP-ALL-4000 , Sentinel R ad Access Management, Rev. 0
AD-RP-ALL-4000, Sentinel Rad Access Management, Rev. 0
AD-RP-ALL-4002 , TLD Issue and Management for
AD-RP-ALL-4002, TLD Issue and Management for Active Workers, Rev. 2
Active Workers, Rev. 2
AD-RP-ALL-4005, Dose Management, Rev. 0
AD-RP-ALL-4005 , Dose Management, Rev. 0
AD-RP-ALL-4007, Exposure File Management, Rev. 1
AD-RP-ALL-4007 , Exposure F ile Management, Rev. 1 AD-RP-ALL-4010 , Internal Dose Assessment, Rev. 0 AD-RP-ALL-9000 , ALARA Program, Rev. 2 AD-RP-ALL-9001 , ALARA Planning, Rev. 0 AI-1602 , ALARA Committee, Rev. 1 2 Areva, FS-156, Fuel Assembly Visual Examination using the Mobile Video Rig, Revision 005
AD-RP-ALL-4010, Internal Dose Assessment, Rev. 0
DOS-4011 , I n Vitro Bioassay, Rev. 0 FP-204 , Auxiliary Building F uel Handling Operations, Rev. 4 FP-601C , Operation of
AD-RP-ALL-9000, ALARA Program, Rev. 2
S pent F uel P ool Handling Bridge FHCR-3 , Rev. 50 FP-601G , Operation of Spent Fuel Pool Handling Monorail FHCR-3A, Rev. 4 HPP-202A , Radiological
AD-RP-ALL-9001, ALARA Planning, Rev. 0
Surveys and
AI-1602, ALARA Committee, Rev. 12
Inspections, Rev. 43
Areva, FS-156, Fuel Assembly Visual Examination using the Mobile Video Rig, Revision 005
Attachment
DOS-4011, In Vitro Bioassay, Rev. 0
FP-204, Auxiliary Building Fuel Handling Operations, Rev. 4
FP-601C, Operation of Spent Fuel Pool Handling Bridge FHCR-3, Rev. 50
FP-601G, Operation of Spent Fuel Pool Handling Monorail FHCR-3A, Rev. 4
HPP-202A, Radiological Surveys and Inspections, Rev. 43
 
HPS-NGGC-0001, Radioactive Material Receipt and Shipping Procedure, Rev. 32
HPS-NGGC-0001, Radioactive Material Receipt and Shipping Procedure, Rev. 32
HPS-NGGC-0002 , V endor Cask Utilization
HPS-NGGC-0002, Vendor Cask Utilization Procedure Rev. 21
Procedure Rev. 21 PT-531, Spent Fuel Pool Handling Bridge Interlock Test (FHCR
PT-531, Spent Fuel Pool Handling Bridge Interlock Test (FHCR-3), Rev. 12
-3), Rev. 12
PT-671, Spent Fuel Pool Handling Bridge (FHCR-3) Load Test, Rev. 10
PT-671 , Spent Fuel Pool Handling Bridge (FHCR
PT0672, Spent Fuel Handling Monorail Interlock and Load Test (FHCR-3A), Rev. 2
-3) Load Test, Rev. 10
SNM-100, Special Nuclear Materials Handling and Accountability Manual, Rev. 50
PT0672 , S pent F uel Handling Monorail Interlock and
WP-105, Radioactive Material Shipping Forms, Rev. 5
L oad Test (FHCR-3A), Rev. 2 SNM-100 , Special Nuclear Materials Handling and Accountability Manual, Rev. 50 WP-105 , Radioactive Material Shipping Forms , Rev. 5 Completed Surveillance Procedures
Completed Surveillance Procedures and Surveys
and Surveys
Survey CR-3-M-20150303-5
Survey CR-3-M-20150303-5 Survey CR-3-M-20150309-5 Survey CR-3-M-20150316-5 Survey CR-3-M-201503 16-10 Survey CR-3-M-20150 413-3
Survey CR-3-M-20150309-5
Survey CR-3-M-20150316-5
Survey CR-3-M-20150316-10
Survey CR-3-M-20150413-3
Miscellaneous
Miscellaneous
ALARA Work Plan, 15-001, Spent Fuel Sipping & Inspection, Rev. 2 Crystal River Plant, Fleet All Priorities Maintenance Backlog KPI
ALARA Work Plan, 15-001, Spent Fuel Sipping & Inspection, Rev. 2
Daily RP Dose Reports, 1/1/2015  
Crystal River Plant, Fleet All Priorities Maintenance Backlog KPI
- 8/12/2015 RP Survey Instructions to Support Ready Warehouse Demolition
Daily RP Dose Reports, 1/1/2015 - 8/12/2015
RWP-1060, CR-3 Fuel Sipping Activities, Rev. 2 Vacuum Sipping Work Order Instructions
RP Survey Instructions to Support Ready Warehouse Demolition
RWP-1060, CR-3 Fuel Sipping Activities, Rev. 2
Vacuum Sipping Work Order Instructions
Work Orders
Work Orders
WO 13532299 01
WO 13532299 01
LIST OF ACRONYMS USED
LIST OF ACRONYMS USED
ADAMS Agency Documentation and Management System
ADAMS                 Agency Documentation and Management System
CFR   Code of Federal Regulations
CFR                   Code of Federal Regulations
CR-3   Crystal River Unit 3
CR-3                   Crystal River Unit 3
Duke Energy
Duke Energy           Duke Energy Florida, Inc.
Duke Energy Florida, Inc
IMC                   Inspection Manual Chapter
. IMC   Inspection Manual Chapter
IP                     Inspection Procedure
IP   Inspection Procedure
NRC                   U.S. Nuclear Regulatory Commission
NRC   U.S. Nuclear Regulatory Commission
RP                     Radiation Protection
RP   Radiation Protection
Attachment
}}
}}

Revision as of 06:27, 31 October 2019

Duke Energy Florida, Inc., Crystal River Unit 3, NRC Inspection Report 05000302/2015009
ML15294A180
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 10/21/2015
From: Racquel Powell
Division of Nuclear Materials Safety I
To: Hobbs T
Duke Energy Florida
References
IR 2015009
Download: ML15294A180 (9)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ber 21, 2015

SUBJECT:

NRC INSPECTION REPORT NO. 05000302/2015009, DUKE ENERGY FLORIDA, INC., CRYSTAL RIVER UNIT 3, CRYSTAL RIVER, FLORIDA

Dear Mr. Hobbs:

On September 30, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its quarterly inspection under Inspection Manual Chapter 2561, Decommissioning Power Reactor Inspection Program," at the permanently shut down Crystal River Nuclear Plant Unit 3 (CR-3). On-site inspections were performed on August 25-27, 2015. In-office reviews of information supplied by Duke Energy Florida, Inc. were also performed during the inspection period. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Phyllis Dixon, Decommissioning Technical Support Manager, and other members of the CR-3 staff on October 5, 2015, and are described in the enclosed report. No findings of safety significance were identified.

In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure(s), and your response, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC document system (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.

Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Radioactive Waste; Decommissioning of Nuclear Facilities; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Steve Hammann, at 610-337-5399, if you have any questions regarding this matter.

Sincerely,

/RA/

Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure: Inspection Report 05000302/2015009 cc w/encl: Distribution via ListServ

EXECUTIVE SUMMARY

Duke Energy

Crystal River Nuclear Plant NRC Inspection Report No. 05000302/2015009 An announced quarterly inspection was completed at CR-3 on September 30, 2015. On-site inspections were conducted on August 25-27, 2015. In-office reviews of information supplied by Duke Energy were also performed during the inspection period. The inspection included a review of site operations, management oversight, site radiological programs, maintenance and surveillance, and decommissioning performance. The inspection consisted of observations by the inspector, interviews with Duke Energy personnel, a review of procedures and records, and plant walk-downs. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561,

Decommissioning Power Reactor Inspection Program."

Based on the results of this inspection, no findings of safety significance were identified.

ii Inspection Report No. 05000302/2015009 G:\WordDocs\Mailed\Insp Letter\LDPR-72.201500910212015.docx

REPORT DETAILS

1.0 Background On February 20, 2013, Duke Energy sent a letter [Agency Documentation and Management System (ADAMS) Accession Number: ML13056A005] to the NRC certifying the permanent cessation of activities and certifying that the fuel had been permanently removed from the reactor. This met the requirements of 10 Code of Federal Regulations (CFR) 50.82(a)(1)(i) and 50.82(a)(1)(ii). As of the end of this reporting period, Crystal River Unit 3 (CR-3) has moved from the Post Operation Transitional Phase of decommissioning to the SAFSTOR phase of decommissioning as described in IMC 2561.

2.0 Post Operation Transition Phase Performance and Status Review

a. Inspection Scope

(Inspection Procedures (IPs) 62801, 71801, 83750, 86750)

The inspector performed an on-site inspection the week of August 25-27, 2015. In-office reviews of information supplied by Duke Energy were also performed during the inspection period. The inspection consisted of observations by the inspector, interviews with Duke Energy personnel, a review of procedures and records, and plant walk-downs.

The inspector reviewed activities and documentation associated with the occupational exposure and radioactive waste management to determine the effectiveness of site radiological programs. The inspector accompanied a CR-3 radiation protection (RP)technician during a plant walk-down which included; checking postings, general area surveys, air sample collection and analysis. The inspector also toured the instrument calibration lab and reviewed the setup of the calibrator and reviewed calibration procedures. The inspector observed work activities associated with the processing, packaging, surveying, and storage of radwaste and reviewed the work package for the most recent shipment of radwaste to verify compliance with the regulations. The inspector reviewed year-to-date dose totals, radiation work permits, and As Low As Reasonably Achievable work plans to verify radiation work activities were pre-planned effectively to limit worker exposure.

The inspector reviewed the completed work package and related procedures completed for the quarterly preventative maintenance of the fuel handling crane to verify that maintenance was being performed within the established frequencies and that the equipment was being properly maintained. The inspector also met with CR-3 maintenance supervisors and discussed staffing levels, how routine maintenance and emergent work is requested, prioritized, and scheduled, and reviewed the current maintenance workload. The inspector reviewed the backlog of maintenance work to assess the age and prioritization of the items.

Inspection Report No. 05000302/2015009 G:\WordDocs\Mailed\Insp Letter\LDPR-72.201500910212015.docx

The inspector observed CR-3 and Areva, Inc. personnel performing visual inspections of spent fuel assemblies in order to assess the material condition of the spent fuel assemblies. The visual inspections are in preparation for the CR-3 campaign to move all fuel assemblies from the spent fuel pool and into dry cask storage. The inspector reviewed the equipment setup, RP coverage of the project, and evaluated CR-3s adherence to procedures.

b. Observations and Findings

The inspector attended pre-job briefings and determined that briefings were thorough and identified the significant potential hazards for the activities to be performed. The inspector determined that survey records were clear and complete and RP staff effectively controlled work activities. The inspector noted most routine surveys, instrument calibrations and daily source checks of instruments are performed on back shift. The inspector also noted that most radwaste has been shipped off-site and several large legacy radwaste items are scheduled to be shipped within the next year.

The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the technical specifications requirements and established procedures. The inspector determined that approximately 20% of maintenance work is preventative maintenance and the rest is emergent work. The inspector also determined that approximately 90% of the maintenance workload is non-complex and does not require a work order.

The inspector noted that the visual inspection of fuel assemblies was being performed using multiple cameras and that all four sides, top, and bottom are viewed and that all visuals are recorded. The inspector verified that a second independent individual views the monitors to verify results and all deformations of fuel assemblies are noted. The inspector noted that CR-3 plans to further test the fuel assemblies with deformations to ensure they will be able to be loaded into dry casks.

c. Conclusions

Based on the results of this inspection, no findings of safety significance were identified.

3.0

Exit Meeting Summary

On October 5, 2015, the inspector presented the inspection results, via teleconference, to Phyllis Dixon, Decommissioning Technical Support Manager, and other members of Duke Energys staff. The inspectors confirmed that proprietary information was not removed from the site.

Inspection Report No. 05000302/2015009 G:\WordDocs\Mailed\Insp Letter\LDPR-72.201500910212015.docx PARTIAL LIST OF PERSONS CONTACTED Licensee K. Ankrum, Finance B. Akins, Radiation Protection and Chemistry Manager J. Campbell, RP Tech P. Dixon, Decommissioning Technical Support Manager J. Gaines, Sr. HR Consultant K. Hirsch, Lead Scientist T. Hobbs, Decommissioning General Manager R. Macko, Sr. Scientist P. Rose, Licensing I. Wilson, General Manager Decommissioning (Acting)

K. Shelton, RP Supervisor J. Stoney, Radwaste Tech D. Sumners, RP Tech M. Van Sicklen, Licensing H. Wojtasinski, Maintenance Supervisor ITEMS OPEN, CLOSED, AND DISCUSSED None LIST OF

DOCUMENTS REVIEWED

Audits and Reports

2014-CR3-QA-01Audit Report

2014-CR3-REW-01 Audit Report

2015-CR3-QA-01 Audit Report

RP Self Assessment 734454-11, Respiratory Protection, Rad Material Storage, Rad Posting &

Labeling, April 2015

Procedures

AD-RP-ALL-4000, Sentinel Rad Access Management, Rev. 0

AD-RP-ALL-4002, TLD Issue and Management for Active Workers, Rev. 2

AD-RP-ALL-4005, Dose Management, Rev. 0

AD-RP-ALL-4007, Exposure File Management, Rev. 1

AD-RP-ALL-4010, Internal Dose Assessment, Rev. 0

AD-RP-ALL-9000, ALARA Program, Rev. 2

AD-RP-ALL-9001, ALARA Planning, Rev. 0

AI-1602, ALARA Committee, Rev. 12

Areva, FS-156, Fuel Assembly Visual Examination using the Mobile Video Rig, Revision 005

DOS-4011, In Vitro Bioassay, Rev. 0

FP-204, Auxiliary Building Fuel Handling Operations, Rev. 4

FP-601C, Operation of Spent Fuel Pool Handling Bridge FHCR-3, Rev. 50

FP-601G, Operation of Spent Fuel Pool Handling Monorail FHCR-3A, Rev. 4

HPP-202A, Radiological Surveys and Inspections, Rev. 43

HPS-NGGC-0001, Radioactive Material Receipt and Shipping Procedure, Rev. 32

HPS-NGGC-0002, Vendor Cask Utilization Procedure Rev. 21

PT-531, Spent Fuel Pool Handling Bridge Interlock Test (FHCR-3), Rev. 12

PT-671, Spent Fuel Pool Handling Bridge (FHCR-3) Load Test, Rev. 10

PT0672, Spent Fuel Handling Monorail Interlock and Load Test (FHCR-3A), Rev. 2

SNM-100, Special Nuclear Materials Handling and Accountability Manual, Rev. 50

WP-105, Radioactive Material Shipping Forms, Rev. 5

Completed Surveillance Procedures and Surveys

Survey CR-3-M-20150303-5

Survey CR-3-M-20150309-5

Survey CR-3-M-20150316-5

Survey CR-3-M-20150316-10

Survey CR-3-M-20150413-3

Miscellaneous

ALARA Work Plan,15-001, Spent Fuel Sipping & Inspection, Rev. 2

Crystal River Plant, Fleet All Priorities Maintenance Backlog KPI

Daily RP Dose Reports, 1/1/2015 - 8/12/2015

RP Survey Instructions to Support Ready Warehouse Demolition

RWP-1060, CR-3 Fuel Sipping Activities, Rev. 2

Vacuum Sipping Work Order Instructions

Work Orders

WO 13532299 01

LIST OF ACRONYMS USED

ADAMS Agency Documentation and Management System

CFR Code of Federal Regulations

CR-3 Crystal River Unit 3

Duke Energy Duke Energy Florida, Inc.

IMC Inspection Manual Chapter

IP Inspection Procedure

NRC U.S. Nuclear Regulatory Commission

RP Radiation Protection

Attachment

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