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{{#Wiki_filter: | {{#Wiki_filter:August 24, 2016 | ||
==SUBJECT:== | ==SUBJECT:== | ||
NRC INSPECTION REPORT NO. 05000302/ | NRC INSPECTION REPORT NO. 05000302/2016002, DUKE ENERGY FLORIDA, INC., CRYSTAL RIVER UNIT 3, CRYSTAL RIVER, FLORIDA | ||
==Dear Mr. Hobbs:== | ==Dear Mr. Hobbs:== | ||
On July 28, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an on-site inspection under Inspection Manual Chapter 2561 , | On July 28, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an on-site inspection under Inspection Manual Chapter 2561, Decommissioning Power Reactor Inspection Program," at the permanently shut down Crystal River Nuclear Plant Unit 3 (CR-3). 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 July 28, 2016, and are described in the enclosed report. No findings of safety significance were identified. | ||
In accordance with 10 CFR 2.390 of the | 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). | 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. | 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 MRoberts for/ | /RA MRoberts for/ | ||
Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure: | |||
Inspection Report 05000302/ | Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety | ||
Enclosure: | |||
Inspection Report 05000302/2016002 | |||
cc w/encl: | |||
Distribution via ListServ | Distribution via ListServ | ||
| Line 41: | Line 49: | ||
Duke Energy | Duke Energy | ||
Crystal River Nuclear Plant NRC Inspection Report No. 05000302/ | Crystal River Nuclear Plant NRC Inspection Report No. 05000302/2016002 | ||
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, | An announced CR-3 decommissioning on-site inspection was performed July 26-28, 2016. The inspection included a review of 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. | ||
Inspection Report No. 05000302/2016002 | |||
=REPORT DETAILS= | =REPORT DETAILS= | ||
1.0 | 1.0 Background | ||
CR-3 is currently in the SAFSTOR phase of decommissioning as described in Inspection Manual Chapter (IMC) 2561. 2.0 Post Operation Transition Phase Performance and Status Review | 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). CR-3 is currently in the SAFSTOR phase of decommissioning as described in Inspection Manual Chapter (IMC) 2561. | ||
2.0 Post Operation Transition Phase Performance and Status Review | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
[Inspection Procedures (IPs) 62801 , 71801, 83750, 84750, | [Inspection Procedures (IPs) 62801, 71801, 83750, 84750, 86750] | ||
The inspector performed an on-site inspection the week of July 26-28, 2016. 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 | The inspector reviewed activities and documentation associated with occupational exposure, radioactive waste management, and effluent and environmental monitoring 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; general area surveys, checking and verifying radiological postings, air sample collection and analysis, checking locked doors and gates, and general housekeeping. The inspector also toured the instrument calibration lab, instrument/counting room, and chemistry lab. The inspector reviewed 2015 dose totals, radiation work permits, and As Low As Reasonably Achievable (ALARA) work plans to verify radiation work activities were pre-planned effectively to limit worker exposure. The inspector performed a walk-down of the radwaste system and site effluent monitoring points to ensure CR-3 properly processes and stores radioactive materials and that radiological environmental monitoring programs (REMP) are effectively implemented. The inspector reviewed procedures, diagrams of effluent monitoring systems, annual REMP report, annual radioactive effluent report, and the Off-Site Dose Calculation Manual. The inspector also reviewed the work package for the most recent shipment of radwaste to verify compliance with the regulations. ` | ||
The inspector reviewed the backlog of maintenance work to assess the age and prioritization of the items. The inspector reviewed the maintenance rule program, periodic assessment, and scoping and performance criteria. | The inspector accompanied a plant systems engineer on a walk-down of key safety systems and equipment important to the defueled condition of the plant. The inspector observed work activities, reviewed work orders and related procedures for the quarterly preventative maintenance of the B chiller 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 supervision 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. The inspector reviewed the maintenance rule program, periodic assessment, and scoping and performance criteria. | ||
Inspection Report No. 05000302/2016002 | Inspection Report No. 05000302/2016002 | ||
The inspector also reviewed the shipping paperwork for the first offsite shipment of new fuel assemblies. | The inspector reviewed work orders, work instructions, and procedures for the new fuel assembly shipping project. The inspector observed CR-3 and Areva, Inc. personnel moving new fuel assemblies into shipping containers to be transported offsite, and evaluated CR-3s adherence to procedures. The inspector also reviewed the shipping paperwork for the first offsite shipment of new fuel assemblies. | ||
The inspector interviewed personnel and reviewed documentation related to the demolition and removal of the Ready Warehouse. The inspector reviewed work orders, work plans, engineering change package, and radiological surveys to verify activities were performed in accordance with plant procedures, technical specifications (TS) and the regulations. The inspector also reviewed work orders and procedures for non-radiological hazardous materials removal from the project. | The inspector interviewed personnel and reviewed documentation related to the demolition and removal of the Ready Warehouse. The inspector reviewed work orders, work plans, engineering change package, and radiological surveys to verify activities were performed in accordance with plant procedures, technical specifications (TS) and the regulations. The inspector also reviewed work orders and procedures for non-radiological hazardous materials removal from the project. | ||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
The inspector determined that survey records were clear and complete, RP staff effectively controlled work activities, and technician training and qualifications were up to date. The inspectors verified that ALARA plans and in | The inspector determined that survey records were clear and complete, RP staff effectively controlled work activities, and technician training and qualifications were up to date. The inspectors verified that ALARA plans and in-progress ALARA reviews were performed as needed and post-ALARA reviews were performed to assess the effectiveness of radiological controls. The inspector noted that the RP staff may be supplemented with contractors depending on the project. The inspector verified that the annual radiological effluent and the annual REMP reports demonstrated that calculated doses were below regulatory dose criteria of 10 Code of Federal Regulations (CFR) 50, Appendix I. The inspector also determined that waste treatment systems were maintained and operated in accordance with site procedures. The inspector verified that effluent releases to the environment were being properly controlled, monitored, and quantified as required by NRC regulations. | ||
-progress ALARA reviews were performed as needed and post | |||
-ALARA reviews were performed to assess the effectiveness of radiological controls. | |||
The inspector noted that the RP staff may be supplemented with contractors depending on the project. | |||
The inspector verified that the annual radiological effluent and the annual REMP reports demonstrated that calculated doses were below regulatory dose criteria of 10 Code of Federal Regulations (CFR) 50, Appendix I. | |||
The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the TS requirements and established procedures. The inspector noted that throughout the inspection period, housekeeping and plant material condition standards were being maintained. The inspector determined that workers followed work plans, surveillance procedures and industrial safety protocols and were aware of job controls specified in work instructions. | |||
The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the TS requirements and established procedures. | |||
The inspector noted that throughout the inspection period | |||
, housekeeping and plant material condition standards were being | |||
The inspector determined that the maintenance backlog is reviewed by site management on a regular basis. | The inspector determined that the maintenance backlog is reviewed by site management on a regular basis. | ||
| Line 108: | Line 89: | ||
The inspector noted that the new fuel assembly shipments are being performed in two phases and is scheduled to be completed in early 2017. | The inspector noted that the new fuel assembly shipments are being performed in two phases and is scheduled to be completed in early 2017. | ||
The inspector determined the pre | The inspector determined the pre-and post-radiological surveys of the Ready Warehouse were adequately performed and the demolition and removal of the warehouse was performed in accordance with site procedures and the regulations. The inspector also determined CR-3 and its contracted workforce conducted the warehouse removal in accordance with licensed requirements. | ||
- and post-radiological surveys of the Ready Warehouse were adequately performed and the demolition and removal of the warehouse was performed in accordance with site procedures and the regulations. | |||
The inspector also determined CR | |||
-3 and its contracted workforce conducted the warehouse removal in accordance with licensed requirements. | |||
Inspection Report No. 05000302/2016002 | Inspection Report No. 05000302/2016002 | ||
| Line 121: | Line 98: | ||
3.0 | 3.0 | ||
===Exit Meeting Summary=== | |||
On July 28, | On July 28, 2016, the inspector presented the inspection results to Phyllis Dixon, Decommissioning Technical Support Manager, and other members of Duke Energys staff. The inspector confirmed that proprietary information was not removed from the site. | ||
Inspection Report No. 05000302/2016002 | |||
PARTIAL LIST OF PERSONS CONTACTED | |||
Licensee K. Ankrum, Finance B. Akins, Radiation Protection and Chemistry Manager C. Burtoff, Lead RP P. Dixon, Decommissioning Technical Support Manager T. Hobbs, Decommissioning General Manager J. Lane, Systems Engineer J. LaPratt, ISFSI PM R. Macko, Sr. Scientist L. McDougal, Maintenance and Operations PM P. Rose, Licensing K. Shelton, RP Supervisor D. Sumners, RP Tech M. Van Sicklen, Licensing T. Worthington, Supervisor Engineering | |||
ITEMS OPEN, CLOSED, AND DISCUSSED | |||
None | |||
LIST OF | |||
=DOCUMENTS REVIEWED= | =DOCUMENTS REVIEWED= | ||
Audits and Reports | Audits and Reports | ||
2015 Radiation Protection Annual Dose Report | 2015 Radiation Protection Annual Dose Report for Members of the Public and Unmonitored | ||
for Members of the Public and Unmonitored | |||
Occupational Individuals in the Restricted Area | Occupational Individuals in the Restricted Area | ||
2016 Prospective Assessment | 2016 Prospective Assessment Dose Monitoring Evaluation | ||
Dose Monitoring Evaluation | Benchmark Report AR Numbers: 758358, 2039163 | ||
Benchmark Report AR | Crystal River Dose Report 2015 | ||
Self-Assessment Report | Self-Assessment Report AR Numbers: 734454-11, 1965865-11, 2008137-11, 2039155, | ||
AR | 1990900-11, 2025556 | ||
Procedures | |||
ADM-0101, Maintenance Rule Program, Rev. 1 | ADM-0101, Maintenance Rule Program, Rev. 1 | ||
ADM-0105, ALARA Planning, Rev. 2 | ADM-0105, ALARA Planning, Rev. 2 | ||
AI-1602, ALARA Committee, Rev. 1 | |||
AI-504, Guidelines for Key Safety Function, Rev. 49 | AI-504, Guidelines for Key Safety Function, Rev. 49 | ||
AI-1810, Asbestos Management and Exposure Control Programs, Rev.11 | AI-1810, Asbestos Management and Exposure Control Programs, Rev.11 | ||
AI-1821, Radioactive | AI-1821, Radioactive Waste Management Program, Rev.0 | ||
Waste Management | |||
Program, Rev.0 | |||
CP-161, Radiological Environmental Monitoring Program, Rev. 8 | CP-161, Radiological Environmental Monitoring Program, Rev. 8 | ||
CP-163, Nuclear Chemistry Quality Control, Rev. 11 | CP-163, Nuclear Chemistry Quality Control, Rev. 11 | ||
CP-9000, Radiological Groundwater Protection, Rev. 1 | CP-9000, Radiological Groundwater Protection, Rev. 1 | ||
DOS-4010, Internal Dose Assessment, Rev. 1 | DOS-4010, Internal Dose Assessment, Rev. 1 | ||
DOS-4011, | DOS-4011, In Vitro Bioassay, Rev. 0 | ||
FP-304, Receiving New Fuel Containers for Batch 19, Rev. 25 | FP-304, Receiving New Fuel Containers for Batch 19, Rev. 25 | ||
FP- | FP-305, Loading and Shipping Batch 19 Fuel Containers to Off-Site, Rev. 13 | ||
-Site, Rev. 13 | |||
Inspection Report No. 05000302/2016002 | Inspection Report No. 05000302/2016002 | ||
Procedures | Procedures (Contd) | ||
FS-278 Mk-B Unused Fuel Inspections, Rev. 3 (Areva, Fuel Field Services) | |||
HPS-0001, Radioactive Material Receipt and Shipping Procedure, Rev. 1 | HPS-0001, Radioactive Material Receipt and Shipping Procedure, Rev. 1 | ||
HPS-1000, Radiation Protection | HPS-1000, Radiation Protection-Conduct of Operations, Rev.2 | ||
-Conduct of Operations, Rev.2 | |||
RSP-101, Basic Radiological Safety Information and Instructions for Radiation Workers, Rev. 57 | RSP-101, Basic Radiological Safety Information and Instructions for Radiation Workers, Rev. 57 | ||
SAF-SUBS-00013, Lead Exposure, Rev. 8 | SAF-SUBS-00013, Lead Exposure, Rev. 8 | ||
WDT-6 , Primary Resin Tank Operations, Rev. 15 WP-210, Sluicing, Loading, Filling, and Venting Waste Disposal Tanks WDT | WDT-6, Primary Resin Tank Operations, Rev. 15 | ||
-15 Through | WP-210, Sluicing, Loading, Filling, and Venting Waste Disposal Tanks WDT-15 Through | ||
WDT-21 | WDT-21 Demineralizer System, Rev 11 | ||
Completed Surveillance Procedures | Completed Surveillance Procedures and Surveys | ||
and Surveys | Radiological Survey CR3-M-20150303-5, CR3-M-20150309-5, CR3-M-20150316-5, CR3-M- | ||
Radiological Survey CR3 | 20150316-10, CR3-M-20150413-3, CR3-M-20160613-2, CR3-M-20160625-1, CR3-M- | ||
-M-20150303-5 , CR3-M-20150309-5 , CR3-M- | 20160415-2, CR3-M-20160426-1, CR3-M-20160512-2 | ||
CHHE-4A, CHHE-4B, CHHE-4C | CR3 Operations Log: CHHE-4A, CHHE-4B, CHHE-4C | ||
Equipment Work History: CHHE-4A, CHHE-4B, CHHE-4C | |||
NESHAP Demolition Asbestos Survey, Ready Warehouse Building, August 18, 2015 | |||
Miscellaneous | Miscellaneous | ||
ALARA Committee Meeting Minutes: April 13, 2016; May 5, 2016; June 10, 2016 | ALARA Committee Meeting Minutes: April 13, 2016; May 5, 2016; June 10, 2016 | ||
ALARA Work Plan | ALARA Work Plan 16-02, 16-03 | ||
16-02, 16-03 | Crystal River Maintenance Backlog | ||
: [[contact::D.H. Griffin Wrecking Co.]], Inc., Work Plan, Crystal River Plant, CR | : [[contact::D.H. Griffin Wrecking Co.]], Inc., Work Plan, Crystal River Plant, CR-3 Ready Warehouse | ||
-3 Ready Warehouse | Radioactive Waste Manifest Packages, 0769-04-0002 and 0769-04-0002, Used Steam | ||
Radioactive Waste Manifest | |||
Packages , 0769-04-0002 and 0769-04-0002, Used Steam | |||
Generators | Generators | ||
In-Progress ALARA | In-Progress ALARA Evaluations 16-02, 16-03 | ||
Maintenance Rule Scoping and Performance Criteria | |||
Off-Site Dose Calculation Manual, Rev 36 | |||
Manual, Rev 36 | Post Job ALARA Critique 16-02, 16-03 | ||
Post Job ALARA Critique | Quarterly Waste Container Inventory | ||
16-02, 16-03 Quarterly Waste Container Inventory | Radioactive Shipment Record, 16-013 | ||
Radioactive Shipment Record, 16 | RP Survey Instructions to Support Ready Warehouse Demolition | ||
-013 RP Survey Instructions to Support Ready Warehouse Demolition | Radioactive Waste Manifest Packages, 0769-04-0002, Used Steam Generator | ||
Radioactive Waste Manifest | Standard Work Instruction (SWI-410090A) - Preparing, Shipping and Receiving of 51032-2 | ||
Packages, 0769-04-0002, Used Steam Generator | Containers Offsite (Areva) | ||
Standard Work Instruction | Standard Work Instruction (SW50303A) - 51032-2 Shipping Container - Packing Fuel Bundles | ||
Offsite (Areva) | |||
-2 | Work Orders | ||
1347909 10 - Ready Warehouse Demolition | |||
- 51032-2 Shipping Container - Packing Fuel Bundles | 1347909 03-Perform Lead and Asbestos Sampling and Abatement | ||
Offsite (Areva) | 20048278 01-CHHE-4A Quarterly Maintenance | ||
1347909 10 | 20043379-05 - load batch 19 fuel assemblies | ||
- Ready Warehouse Demolition | |||
1347909 03 | |||
- Perform Lead and Asbestos Sampling and Abatement | |||
20048278 | |||
20043379-05 - load batch 19 fuel assemblies | |||
Inspection Report No. 05000302/2016002 | Inspection Report No. 05000302/2016002 | ||
LIST OF ACRONYMS USED | LIST OF ACRONYMS USED | ||
ADAMS | ADAMS | ||
ALARA | Agency Documentation and Management System | ||
CFR | ALARA | ||
CR-3 | As Low As Reasonably Achievable | ||
CFR | |||
Code of Federal Regulations | |||
CR-3 | |||
Crystal River Unit 3 | |||
Duke Energy | Duke Energy | ||
Duke Energy Florida, Inc | Duke Energy Florida, Inc. | ||
IMC | |||
IP | |||
NRC | Inspection Manual Chapter | ||
REMP | IP | ||
RP | |||
TS | Inspection Procedure | ||
NRC | |||
U.S. Nuclear Regulatory Commission | |||
REMP | |||
Radiological Environmental Monitoring Program | |||
RP | |||
Radiation Protection | |||
TS | |||
Technical Specifications | |||
}} | }} | ||
Latest revision as of 20:47, 9 January 2025
| ML16238A062 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 08/24/2016 |
| From: | Racquel Powell Division of Nuclear Materials Safety I |
| To: | Hobbs T Duke Energy Florida |
| References | |
| IR 2016002 | |
| Download: ML16238A062 (11) | |
Text
August 24, 2016
SUBJECT:
NRC INSPECTION REPORT NO. 05000302/2016002, DUKE ENERGY FLORIDA, INC., CRYSTAL RIVER UNIT 3, CRYSTAL RIVER, FLORIDA
Dear Mr. Hobbs:
On July 28, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an on-site inspection under Inspection Manual Chapter 2561, Decommissioning Power Reactor Inspection Program," at the permanently shut down Crystal River Nuclear Plant Unit 3 (CR-3). 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 July 28, 2016, 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).
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,
/RA MRoberts for/
Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety
Enclosure:
Inspection Report 05000302/2016002
cc w/encl:
Distribution via ListServ
EXECUTIVE SUMMARY
Duke Energy
Crystal River Nuclear Plant NRC Inspection Report No. 05000302/2016002
An announced CR-3 decommissioning on-site inspection was performed July 26-28, 2016. The inspection included a review of 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.
Inspection Report No. 05000302/2016002
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). CR-3 is currently in the SAFSTOR phase of decommissioning as described in Inspection Manual Chapter (IMC) 2561.
2.0 Post Operation Transition Phase Performance and Status Review
a. Inspection Scope
[Inspection Procedures (IPs) 62801, 71801, 83750, 84750, 86750]
The inspector performed an on-site inspection the week of July 26-28, 2016. 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 occupational exposure, radioactive waste management, and effluent and environmental monitoring 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; general area surveys, checking and verifying radiological postings, air sample collection and analysis, checking locked doors and gates, and general housekeeping. The inspector also toured the instrument calibration lab, instrument/counting room, and chemistry lab. The inspector reviewed 2015 dose totals, radiation work permits, and As Low As Reasonably Achievable (ALARA) work plans to verify radiation work activities were pre-planned effectively to limit worker exposure. The inspector performed a walk-down of the radwaste system and site effluent monitoring points to ensure CR-3 properly processes and stores radioactive materials and that radiological environmental monitoring programs (REMP) are effectively implemented. The inspector reviewed procedures, diagrams of effluent monitoring systems, annual REMP report, annual radioactive effluent report, and the Off-Site Dose Calculation Manual. The inspector also reviewed the work package for the most recent shipment of radwaste to verify compliance with the regulations. `
The inspector accompanied a plant systems engineer on a walk-down of key safety systems and equipment important to the defueled condition of the plant. The inspector observed work activities, reviewed work orders and related procedures for the quarterly preventative maintenance of the B chiller 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 supervision 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. The inspector reviewed the maintenance rule program, periodic assessment, and scoping and performance criteria.
Inspection Report No. 05000302/2016002
The inspector reviewed work orders, work instructions, and procedures for the new fuel assembly shipping project. The inspector observed CR-3 and Areva, Inc. personnel moving new fuel assemblies into shipping containers to be transported offsite, and evaluated CR-3s adherence to procedures. The inspector also reviewed the shipping paperwork for the first offsite shipment of new fuel assemblies.
The inspector interviewed personnel and reviewed documentation related to the demolition and removal of the Ready Warehouse. The inspector reviewed work orders, work plans, engineering change package, and radiological surveys to verify activities were performed in accordance with plant procedures, technical specifications (TS) and the regulations. The inspector also reviewed work orders and procedures for non-radiological hazardous materials removal from the project.
b. Observations and Findings
The inspector determined that survey records were clear and complete, RP staff effectively controlled work activities, and technician training and qualifications were up to date. The inspectors verified that ALARA plans and in-progress ALARA reviews were performed as needed and post-ALARA reviews were performed to assess the effectiveness of radiological controls. The inspector noted that the RP staff may be supplemented with contractors depending on the project. The inspector verified that the annual radiological effluent and the annual REMP reports demonstrated that calculated doses were below regulatory dose criteria of 10 Code of Federal Regulations (CFR) 50, Appendix I. The inspector also determined that waste treatment systems were maintained and operated in accordance with site procedures. The inspector verified that effluent releases to the environment were being properly controlled, monitored, and quantified as required by NRC regulations.
The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the TS requirements and established procedures. The inspector noted that throughout the inspection period, housekeeping and plant material condition standards were being maintained. The inspector determined that workers followed work plans, surveillance procedures and industrial safety protocols and were aware of job controls specified in work instructions.
The inspector determined that the maintenance backlog is reviewed by site management on a regular basis.
The inspector noted that the new fuel assembly shipments are being performed in two phases and is scheduled to be completed in early 2017.
The inspector determined the pre-and post-radiological surveys of the Ready Warehouse were adequately performed and the demolition and removal of the warehouse was performed in accordance with site procedures and the regulations. The inspector also determined CR-3 and its contracted workforce conducted the warehouse removal in accordance with licensed requirements.
Inspection Report No. 05000302/2016002
c. Conclusions
Based on the results of this inspection, no findings of safety significance were identified.
3.0
Exit Meeting Summary
On July 28, 2016, the inspector presented the inspection results to Phyllis Dixon, Decommissioning Technical Support Manager, and other members of Duke Energys staff. The inspector confirmed that proprietary information was not removed from the site.
Inspection Report No. 05000302/2016002
PARTIAL LIST OF PERSONS CONTACTED
Licensee K. Ankrum, Finance B. Akins, Radiation Protection and Chemistry Manager C. Burtoff, Lead RP P. Dixon, Decommissioning Technical Support Manager T. Hobbs, Decommissioning General Manager J. Lane, Systems Engineer J. LaPratt, ISFSI PM R. Macko, Sr. Scientist L. McDougal, Maintenance and Operations PM P. Rose, Licensing K. Shelton, RP Supervisor D. Sumners, RP Tech M. Van Sicklen, Licensing T. Worthington, Supervisor Engineering
ITEMS OPEN, CLOSED, AND DISCUSSED
None
LIST OF
DOCUMENTS REVIEWED
Audits and Reports
2015 Radiation Protection Annual Dose Report for Members of the Public and Unmonitored
Occupational Individuals in the Restricted Area
2016 Prospective Assessment Dose Monitoring Evaluation
Benchmark Report AR Numbers: 758358, 2039163
Crystal River Dose Report 2015
Self-Assessment Report AR Numbers: 734454-11, 1965865-11, 2008137-11, 2039155,
1990900-11, 2025556
Procedures
ADM-0101, Maintenance Rule Program, Rev. 1
ADM-0105, ALARA Planning, Rev. 2
AI-1602, ALARA Committee, Rev. 1
AI-504, Guidelines for Key Safety Function, Rev. 49
AI-1810, Asbestos Management and Exposure Control Programs, Rev.11
AI-1821, Radioactive Waste Management Program, Rev.0
CP-161, Radiological Environmental Monitoring Program, Rev. 8
CP-163, Nuclear Chemistry Quality Control, Rev. 11
CP-9000, Radiological Groundwater Protection, Rev. 1
DOS-4010, Internal Dose Assessment, Rev. 1
DOS-4011, In Vitro Bioassay, Rev. 0
FP-304, Receiving New Fuel Containers for Batch 19, Rev. 25
FP-305, Loading and Shipping Batch 19 Fuel Containers to Off-Site, Rev. 13
Inspection Report No. 05000302/2016002
Procedures (Contd)
FS-278 Mk-B Unused Fuel Inspections, Rev. 3 (Areva, Fuel Field Services)
HPS-0001, Radioactive Material Receipt and Shipping Procedure, Rev. 1
HPS-1000, Radiation Protection-Conduct of Operations, Rev.2
RSP-101, Basic Radiological Safety Information and Instructions for Radiation Workers, Rev. 57
SAF-SUBS-00013, Lead Exposure, Rev. 8
WDT-6, Primary Resin Tank Operations, Rev. 15
WP-210, Sluicing, Loading, Filling, and Venting Waste Disposal Tanks WDT-15 Through
WDT-21 Demineralizer System, Rev 11
Completed Surveillance Procedures and Surveys
Radiological Survey CR3-M-20150303-5, CR3-M-20150309-5, CR3-M-20150316-5, CR3-M-
20150316-10, CR3-M-20150413-3, CR3-M-20160613-2, CR3-M-20160625-1, CR3-M-
20160415-2, CR3-M-20160426-1, CR3-M-20160512-2
CR3 Operations Log: CHHE-4A, CHHE-4B, CHHE-4C
Equipment Work History: CHHE-4A, CHHE-4B, CHHE-4C
NESHAP Demolition Asbestos Survey, Ready Warehouse Building, August 18, 2015
Miscellaneous
ALARA Committee Meeting Minutes: April 13, 2016; May 5, 2016; June 10, 2016
ALARA Work Plan 16-02, 16-03
Crystal River Maintenance Backlog
- D.H. Griffin Wrecking Co., Inc., Work Plan, Crystal River Plant, CR-3 Ready Warehouse
Radioactive Waste Manifest Packages, 0769-04-0002 and 0769-04-0002, Used Steam
Generators
In-Progress ALARA Evaluations 16-02, 16-03
Maintenance Rule Scoping and Performance Criteria
Off-Site Dose Calculation Manual, Rev 36
Post Job ALARA Critique 16-02, 16-03
Quarterly Waste Container Inventory
Radioactive Shipment Record,16-013
RP Survey Instructions to Support Ready Warehouse Demolition
Radioactive Waste Manifest Packages, 0769-04-0002, Used Steam Generator
Standard Work Instruction (SWI-410090A) - Preparing, Shipping and Receiving of 51032-2
Containers Offsite (Areva)
Standard Work Instruction (SW50303A) - 51032-2 Shipping Container - Packing Fuel Bundles
Offsite (Areva)
Work Orders
1347909 10 - Ready Warehouse Demolition
1347909 03-Perform Lead and Asbestos Sampling and Abatement
20048278 01-CHHE-4A Quarterly Maintenance
20043379-05 - load batch 19 fuel assemblies
Inspection Report No. 05000302/2016002
LIST OF ACRONYMS USED
Agency Documentation and Management System
As Low As Reasonably Achievable
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
Radiological Environmental Monitoring Program
Radiation Protection
TS
Technical Specifications