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On May 22, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at Crystal River Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on May 22, 2008, with you and other members of your staff. | On May 22, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at Crystal River Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on May 22, 2008, with you and other members of your staff. | ||
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission | The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission=s rules and regulations and with the conditions of your license. | ||
=s rules and regulations and with the conditions of your license | |||
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading- rm/adams.html (the Public Electronic Reading Room). | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified. | ||
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
Sincerely, | Sincerely, | ||
/RA/ Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-302 License Nos. DPR-72 | /RA/ | ||
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-302 License Nos. DPR-72 | |||
===Enclosure:=== | ===Enclosure:=== | ||
NRC Inspection Report No. 05000302/2008501 W/Attachment: Supplemental Information | NRC Inspection Report No. 05000302/2008501 W/Attachment: Supplemental Information ( | ||
( | |||
REGION II== | REGION II== | ||
Docket Nos: 50-302 License Nos: DPR-72 Report Nos: 05000302/2008501 Licensee: Progress Energy Florida (Florida Power Corporation) | |||
Docket Nos: 50-302 | Facility: Crystal River, Unit 3 Location: Crystal River Florida Dates: May 19-22, 2008 Inspector: Lee Miller, Senior Emergency Preparedness Inspector Jim Dodson, Senior Project Engineer Martha Barillas, Resident Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure | ||
License Nos: DPR-72 | |||
Report Nos: 05000302/2008501 | |||
Licensee: Progress Energy Florida (Florida Power Corporation) | |||
Facility: Crystal River, Unit 3 | |||
Location: Crystal River Florida | |||
Dates: May 19-22, 2008 | |||
Inspector: Lee Miller, Senior Emergency | |||
Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure | |||
=SUMMARY OF FINDINGS= | =SUMMARY OF FINDINGS= | ||
IR 0500302/2008-501; 5/19/2008 - 5/22/2008; Crystal River Unit 3; Baseline Inspection. | IR 0500302/2008-501; 5/19/2008 - 5/22/2008; Crystal River Unit 3; Baseline Inspection. | ||
The report covered an announced inspection by a regional emergency preparedness inspector, a resident inspector and a regional project engineer. The NRC | The report covered an announced inspection by a regional emergency preparedness inspector, a resident inspector and a regional project engineer. The NRC=s program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process.@ | ||
=s program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process. | |||
===NRC-Identified and Self-Revealing Findings=== | |||
=== | |||
No findings of significance were identified. | No findings of significance were identified. | ||
=== | ===Licensee-Identified Violations=== | ||
. | . | ||
None | None | ||
| Line 79: | Line 60: | ||
==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
===Cornerstone: | ===Cornerstone: Emergency Preparedness=== | ||
1EP1 Exercise Evaluation | 1EP1 Exercise Evaluation | ||
| Line 87: | Line 68: | ||
The onsite inspection consisted of the following review and assessment: | The onsite inspection consisted of the following review and assessment: | ||
* The adequacy of the | * The adequacy of the licensees performance in the biennial exercise conducted on May 21, 2008, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards (RSPSs) in 10 CFR 50.47 (b)(4), (5), (9), and (10),which address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively. | ||
which address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively. | * The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities and Emergency Plan commitments. The facilities assessed were the Control Room simulator, Technical Support Center (TSC), Operations Support Center (OSC) and Emergency Operations Facility (EOF). | ||
* The overall adequacy of the | * Other performance areas besides the RSPS, such as the emergency response organizations (ERO) recognition of abnormal plant conditions, command and control, intra- and inter-facility communications, prioritization of mitigation activities, utilization of repair and field monitoring teams, interface with offsite agencies, and the overall implementation of the emergency plan and its implementing procedures. | ||
* Other performance areas besides the RSPS, such as the emergency response | |||
* Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) exercise reports to determine effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14). | * Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) exercise reports to determine effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14). | ||
* The post-exercise critique process and the presentation to the licensee's senior management conducted on May 22, 2008, to evaluate the | * The post-exercise critique process and the presentation to the licensee's senior management conducted on May 22, 2008, to evaluate the licensees self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50 Appendix E.IV.F.2.g. | ||
The inspector reviewed various documents which are listed in the Attachment to this report. | The inspector reviewed various documents which are listed in the Attachment to this report. | ||
| Line 98: | Line 78: | ||
====b. Findings==== | ====b. Findings==== | ||
No findings of significance were identified. | No findings of significance were identified. | ||
1EP4 Emergency Action Level and Emergency Plan Changes | |||
1EP4 | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
Since the last NRC inspection of this program area, Revision 27 of the Radiological Emergency Response Plan was implemented based on the | Since the last NRC inspection of this program area, Revision 27 of the Radiological Emergency Response Plan was implemented based on the licensees determination, in accordance with 10 CFR 50.54(q), that the changes resulted in no decrease in the effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspector conducted a sampling review of the Plan changes and implementing procedure changes made between May 2007 and May 20078 to evaluate for potential decreases in effectiveness of the Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety. | ||
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, AEmergency Action Level and Emergency Plan Changes. | The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, AEmergency Action Level and Emergency Plan Changes.@ The applicable planning standard (PS), 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. | ||
@ | |||
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the Emergency Action Level (EAL) and emergency plan changes on an annual basis. | The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the Emergency Action Level (EAL) and emergency plan changes on an annual basis. | ||
| Line 118: | Line 95: | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
===Cornerstone: | ===Cornerstone: Emergency Preparedness=== | ||
The inspector sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspector reviewed the period from April 1, 2007 through March 31, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory Assessment Indicator Guideline,@ Revision 5, were used to verify the basis in reporting for each data element. | The inspector sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspector reviewed the period from April 1, 2007 through March 31, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory Assessment Indicator Guideline,@ Revision 5, were used to verify the basis in reporting for each data element. | ||
$ Emergency Response Organization Drill/Exercise Performance (DEP) | |||
$ Emergency Response Organization Readiness (ERO) | $ Emergency Response Organization Readiness (ERO) | ||
$ Alert and Notification System Reliability (ANS) | $ Alert and Notification System Reliability (ANS) | ||
The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for | The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspector also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report. | ||
Reviewed documents are listed in the Attachment to this report. | Reviewed documents are listed in the Attachment to this report. | ||
| Line 131: | Line 108: | ||
====b. Findings==== | ====b. Findings==== | ||
No findings of significance were identified. | No findings of significance were identified. | ||
{{a|4OA6}} | |||
{{a|4OA6}} | |||
==4OA6 Meetings, including Exit== | ==4OA6 Meetings, including Exit== | ||
| Line 144: | Line 120: | ||
===Licensee personnel=== | ===Licensee personnel=== | ||
: [[contact::D. Young Vice President - Crystal River]], Unit 3 | : [[contact::D. Young Vice President - Crystal River]], Unit 3 | ||
: [[contact::M. Annacone Plant Manager - Crystal River]], Unit 3 | : [[contact::M. Annacone Plant Manager - Crystal River]], Unit 3 | ||
P. Gerardin Nuclear Assessment Section | P. Gerardin Nuclear Assessment Section | ||
P. Dixon Nuclear Assessment Section - Manager | P. Dixon Nuclear Assessment Section - Manager | ||
T. Pilo | T. Pilo Fleet Coordinator - Emergency Preparedness | ||
D. Herrin | D. Herrin Licensing & Regulatory Programs | ||
J. Stephenson Emergency Preparedness | J. Stephenson Emergency Preparedness | ||
==LIST OF DOCUMENTS REVIEWED== | ==LIST OF DOCUMENTS REVIEWED== | ||
}} | }} | ||
Latest revision as of 03:37, 22 December 2019
| ML081770188 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/25/2008 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB1 |
| To: | Young D Florida Power Corp |
| References | |
| IR-08-501 | |
| Download: ML081770188 (12) | |
Text
une 25, 2008
SUBJECT:
CRYSTAL RIVER UNIT 3 - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000302/2008501
Dear Mr. Young:
On May 22, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at Crystal River Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on May 22, 2008, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission=s rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-302 License Nos. DPR-72
Enclosure:
NRC Inspection Report No. 05000302/2008501 W/Attachment: Supplemental Information (
REGION II==
Docket Nos: 50-302 License Nos: DPR-72 Report Nos: 05000302/2008501 Licensee: Progress Energy Florida (Florida Power Corporation)
Facility: Crystal River, Unit 3 Location: Crystal River Florida Dates: May 19-22, 2008 Inspector: Lee Miller, Senior Emergency Preparedness Inspector Jim Dodson, Senior Project Engineer Martha Barillas, Resident Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 0500302/2008-501; 5/19/2008 - 5/22/2008; Crystal River Unit 3; Baseline Inspection.
The report covered an announced inspection by a regional emergency preparedness inspector, a resident inspector and a regional project engineer. The NRC=s program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process.@
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
Licensee-Identified Violations
.
None
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP1 Exercise Evaluation
a. Inspection Scope
Prior to the inspection activity, the inspector conducted an in-office review of the exercise objectives and scenario submitted to the NRC to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14). This inspection activity represents one sample on a biennial cycle.
The onsite inspection consisted of the following review and assessment:
- The adequacy of the licensees performance in the biennial exercise conducted on May 21, 2008, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards (RSPSs) in 10 CFR 50.47 (b)(4), (5), (9), and (10),which address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively.
- The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities and Emergency Plan commitments. The facilities assessed were the Control Room simulator, Technical Support Center (TSC), Operations Support Center (OSC) and Emergency Operations Facility (EOF).
- Other performance areas besides the RSPS, such as the emergency response organizations (ERO) recognition of abnormal plant conditions, command and control, intra- and inter-facility communications, prioritization of mitigation activities, utilization of repair and field monitoring teams, interface with offsite agencies, and the overall implementation of the emergency plan and its implementing procedures.
- Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) exercise reports to determine effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14).
- The post-exercise critique process and the presentation to the licensee's senior management conducted on May 22, 2008, to evaluate the licensees self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50 Appendix E.IV.F.2.g.
The inspector reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
1EP4 Emergency Action Level and Emergency Plan Changes
a. Inspection Scope
Since the last NRC inspection of this program area, Revision 27 of the Radiological Emergency Response Plan was implemented based on the licensees determination, in accordance with 10 CFR 50.54(q), that the changes resulted in no decrease in the effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspector conducted a sampling review of the Plan changes and implementing procedure changes made between May 2007 and May 20078 to evaluate for potential decreases in effectiveness of the Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, AEmergency Action Level and Emergency Plan Changes.@ The applicable planning standard (PS), 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the Emergency Action Level (EAL) and emergency plan changes on an annual basis.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
Cornerstone: Emergency Preparedness
The inspector sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspector reviewed the period from April 1, 2007 through March 31, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory Assessment Indicator Guideline,@ Revision 5, were used to verify the basis in reporting for each data element.
$ Emergency Response Organization Drill/Exercise Performance (DEP)
$ Emergency Response Organization Readiness (ERO)
$ Alert and Notification System Reliability (ANS)
The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspector also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report.
Reviewed documents are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Meetings, including Exit
On May 22, 2008, the lead inspector presented the inspection results to Mr. D. Young and other members of his staff. The inspector confirmed that proprietary information was not provided during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
P. Gerardin Nuclear Assessment Section
P. Dixon Nuclear Assessment Section - Manager
T. Pilo Fleet Coordinator - Emergency Preparedness
D. Herrin Licensing & Regulatory Programs
J. Stephenson Emergency Preparedness