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| issue date = 04/30/2008 | | issue date = 04/30/2008 | ||
| title = IR 05000400-08-501, on 04/07/2008 - 4/10/2008, Shearon Harris Nuclear Power Plant, Baseline Inspection | | title = IR 05000400-08-501, on 04/07/2008 - 4/10/2008, Shearon Harris Nuclear Power Plant, Baseline Inspection | ||
| author name = Bonser B | | author name = Bonser B | ||
| author affiliation = NRC/RGN-II/DRS/PSB1 | | author affiliation = NRC/RGN-II/DRS/PSB1 | ||
| addressee name = Duncan R | | addressee name = Duncan R | ||
| addressee affiliation = Carolina Power & Light Co | | addressee affiliation = Carolina Power & Light Co | ||
| docket = 05000400 | | docket = 05000400 | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:ril 30, 2008 | ||
==SUBJECT:== | |||
SHEARON HARRIS NUCLEAR POWER PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000400/2008501 | |||
==Dear Mr. Duncan:== | ==Dear Mr. Duncan:== | ||
Line 30: | Line 28: | ||
Burton and other members of your staff. | Burton 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 | |||
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). | |||
Docket Nos. 50-400 License Nos. NPF-63 | Sincerely, | ||
/RA/ | |||
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-400 License Nos. NPF-63 | |||
===Enclosure:=== | ===Enclosure:=== | ||
NRC Inspection Report No. 05000400/2008501 W | NRC Inspection Report No. 05000400/2008501 W/Attachment: Supplemental Information ( | ||
Supplemental Information | |||
( | |||
REGION II== | |||
Docket Nos: 50-400 License Nos: NPF-63 Report Nos: 05000400/2008501 Licensee: Carolina Power and Light Company Facility: Shearon Harris Nuclear Power Plant, Unit 1 Location: New Hill, NC Dates: April 07-10, 2008 Inspector: Lee Miller, Senior Emergency Preparedness Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety | |||
Docket Nos: 50-400 | |||
License Nos: NPF-63 | |||
Report Nos: 05000400/2008501 | |||
Licensee: Carolina Power and Light Company | |||
Facility: Shearon Harris Nuclear Power Plant, Unit 1 | |||
Location: New Hill, NC | |||
Dates: April 07-10, 2008 | |||
Inspector: Lee Miller, Senior Emergency | |||
Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety | |||
=SUMMARY OF FINDINGS= | =SUMMARY OF FINDINGS= | ||
IR 05000400/2008-501; 04/07/2008 - 4/10/2008; Shearon Harris Nuclear Power Plant; Baseline | IR 05000400/2008-501; 04/07/2008 - 4/10/2008; Shearon Harris Nuclear Power Plant; Baseline | ||
Inspection. | Inspection. | ||
The report covered an announced inspection by one emergency preparedness inspector. The | The report covered an announced inspection by one emergency preparedness inspector. The NRC=s program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process.@ | ||
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. | No findings of significance were identified. | ||
=== | ===Licensee-Identified Violations=== | ||
. | . | ||
None | None | ||
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==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
===Cornerstone:=== | ===Cornerstone: Emergency Preparedness=== | ||
1EP2 | 1EP2 Alert and Notification System Testing | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
The inspector evaluated the adequacy of licensee | The inspector evaluated the adequacy of licensee=s methods for testing the alert and notification system in accordance with NRC Inspection Procedure 71114, Attachment 02, AAlert and Notification System Evaluation@. The applicable planning standard 10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D requirements were used as reference criteria. The criteria contained in NUREG-0654, ACriteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,@ Revision 1, was also used as a reference. | ||
=s methods for testing the alert and notification system in accordance with NRC Inspection Procedure 71114, Attachment 02, AAlert and Notification System Evaluation | |||
@. The applicable planning standard 10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D requirements were used as reference criteria. The criteria contained in NUREG-0654, ACriteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,@ Revision 1, was also used as a reference. | |||
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the alert and notification system on an biennial basis. | The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the alert and notification system on an biennial basis. | ||
Line 148: | Line 74: | ||
====b. Findings==== | ====b. Findings==== | ||
No findings of significance were identified. | No findings of significance were identified. | ||
1EP3 Emergency Response Organization Augmentation | |||
1EP3 | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
The inspector reviewed the licensee | The inspector reviewed the licensee=s Emergency Response Organization (ERO)augmentation staffing requirements and process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The qualification records of key position ERO personnel were reviewed to ensure all ERO qualifications were current. A sample of problems identified from augmentation drills or system tests performed since the last inspection were reviewed to assess the effectiveness of corrective actions. | ||
=s Emergency Response Organization (ERO) augmentation staffing requirements and process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The qualification records of key position ERO personnel were reviewed to ensure all ERO qualifications were current. A sample of problems identified from | |||
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 03, AEmergency Response Organization Staffing and Augmentation System. | The inspection was conducted in accordance with NRC Inspection Procedure 71114, 03, AEmergency Response Organization Staffing and Augmentation System.@ | ||
The applicable planning standard, 10 CFR 50.47(b)(2) 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 ERO staffing and augmentation system on a biennial basis. | The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the ERO staffing and augmentation system on a biennial basis. | ||
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====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==== | ||
The inspector | The inspector=s review of revisions to the emergency plan, implementing procedures, and Emergency Action Level (EAL) changes was performed to determine that changes had not decreased the effectiveness of the plan. The inspector evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures, and EAL changes. The inspector reviewed Shearon Harris Emergency Plan revision 46 and changes to the implementing procedures from February 2007 to February 2008. | ||
=s review of revisions to the emergency plan, implementing procedures, and Emergency Action Level (EAL) changes was performed to determine that changes had not decreased the effectiveness of the plan. The inspector evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures, and EAL changes. The inspector reviewed Shearon Harris Emergency Plan revision 46 and changes to the implementing procedures from February 2007 to February 2008 | |||
@ | 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 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 EAL and emergency plan changes on an annual basis. | ||
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====b. Findings==== | ====b. Findings==== | ||
No findings of significance were identified. | No findings of significance were identified. | ||
1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies | |||
1EP5 | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
The inspector reviewed the corrective actions identified through the EP program to determine the significance of the issues and to determine if repeat problems were occurring. The facility | The inspector reviewed the corrective actions identified through the EP program to determine the significance of the issues and to determine if repeat problems were occurring. The facility=s self-assessments and audits were reviewed to assess the licensee=s ability to be self-critical, thus avoiding complacency and degradation of their EP program. In addition, inspector reviewed licensee=s self-assessments and audits to assess the completeness and effectiveness of all EP-related corrective actions. | ||
=s self-assessments and audits were reviewed to assess the licensee=s ability to be self-critical, thus avoiding complacency and degradation of their EP program. In addition, inspector reviewed licensee | |||
=s self-assessments and audits to assess the completeness and effectiveness of all EP-related corrective actions. | |||
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 05, ACorrection of Emergency Preparedness Weaknesses. | The inspection was conducted in accordance with NRC Inspection Procedure 71114, 05, ACorrection of Emergency Preparedness Weaknesses.@ The applicable planning standard, 10 CFR 50.47(b)(14) 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 correction of emergency preparedness weaknesses on a biennial basis. | The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the correction of emergency preparedness weaknesses on a biennial basis. | ||
Findings | Findings No findings of significance were identified. | ||
==OTHER ACTIVITIES== | ==OTHER ACTIVITIES== | ||
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====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 January 2007 through December 2007. 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 January 2007 through December 2007. 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 213: | Line 126: | ||
====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 226: | Line 138: | ||
===Licensee personnel=== | ===Licensee personnel=== | ||
C. Burton Director Site Operations | |||
C. Burton Director Site Operations | K. Henderson Plant General Manager | ||
K. Henderson Plant General Manager | P. Mentel Manager Site Support Services (Acting) | ||
P. Mentel Manager Site Support Services (Acting) | C. Kamilaris Manager Nuclear Assessment | ||
C. Kamilaris Manager Nuclear Assessment | T. Pilo Fleet Coordinator - Emergency Preparedness | ||
T. Pilo | J. Overly Emergency Preparedness Supervisor | ||
J. Overly | D. McGee Manager Shift Operations | ||
D. McGee | M. Wallace Senior Specialist - Licensing | ||
M. Wallace Senior Specialist - Licensing | |||
==LIST OF DOCUMENTS REVIEWED== | ==LIST OF DOCUMENTS REVIEWED== | ||
}} | }} |
Latest revision as of 05:21, 22 December 2019
ML081210690 | |
Person / Time | |
---|---|
Site: | Harris |
Issue date: | 04/30/2008 |
From: | Brian Bonser NRC/RGN-II/DRS/PSB1 |
To: | Duncan R Carolina Power & Light Co |
References | |
IR-08-501 | |
Download: ML081210690 (10) | |
Text
ril 30, 2008
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000400/2008501
Dear Mr. Duncan:
On April 10, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at Shearon Harris Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on April 10, 2008, with Mr. C.
Burton 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. 50-400 License Nos. NPF-63
Enclosure:
NRC Inspection Report No. 05000400/2008501 W/Attachment: Supplemental Information (
REGION II==
Docket Nos: 50-400 License Nos: NPF-63 Report Nos: 05000400/2008501 Licensee: Carolina Power and Light Company Facility: Shearon Harris Nuclear Power Plant, Unit 1 Location: New Hill, NC Dates: April 07-10, 2008 Inspector: Lee Miller, Senior Emergency Preparedness Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety
SUMMARY OF FINDINGS
IR 05000400/2008-501; 04/07/2008 - 4/10/2008; Shearon Harris Nuclear Power Plant; Baseline
Inspection.
The report covered an announced inspection by one emergency preparedness inspector. 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
1EP2 Alert and Notification System Testing
a. Inspection Scope
The inspector evaluated the adequacy of licensee=s methods for testing the alert and notification system in accordance with NRC Inspection Procedure 71114, Attachment 02, AAlert and Notification System Evaluation@. The applicable planning standard 10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D requirements were used as reference criteria. The criteria contained in NUREG-0654, ACriteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,@ Revision 1, was also used as a reference.
The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the alert and notification system on an biennial basis.
b. Findings
No findings of significance were identified.
1EP3 Emergency Response Organization Augmentation
a. Inspection Scope
The inspector reviewed the licensee=s Emergency Response Organization (ERO)augmentation staffing requirements and process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The qualification records of key position ERO personnel were reviewed to ensure all ERO qualifications were current. A sample of problems identified from augmentation drills or system tests performed since the last inspection were reviewed to assess the effectiveness of corrective actions.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 03, AEmergency Response Organization Staffing and Augmentation System.@
The applicable planning standard, 10 CFR 50.47(b)(2) 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 ERO staffing and augmentation system on a biennial basis.
b. Findings
No findings of significance were identified.
1EP4 Emergency Action Level and Emergency Plan Changes
a. Inspection Scope
The inspector=s review of revisions to the emergency plan, implementing procedures, and Emergency Action Level (EAL) changes was performed to determine that changes had not decreased the effectiveness of the plan. The inspector evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures, and EAL changes. The inspector reviewed Shearon Harris Emergency Plan revision 46 and changes to the implementing procedures from February 2007 to February 2008.
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 EAL and emergency plan changes on an annual basis.
b. Findings
No findings of significance were identified.
1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies
a. Inspection Scope
The inspector reviewed the corrective actions identified through the EP program to determine the significance of the issues and to determine if repeat problems were occurring. The facility=s self-assessments and audits were reviewed to assess the licensee=s ability to be self-critical, thus avoiding complacency and degradation of their EP program. In addition, inspector reviewed licensee=s self-assessments and audits to assess the completeness and effectiveness of all EP-related corrective actions.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 05, ACorrection of Emergency Preparedness Weaknesses.@ The applicable planning standard, 10 CFR 50.47(b)(14) 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 correction of emergency preparedness weaknesses on a biennial basis.
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 January 2007 through December 2007. 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 April 10, 2008, the lead inspector presented the inspection results to Mr. C. Burton and other members of your staff. The inspector confirmed that proprietary information was not provided during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
C. Burton Director Site Operations
K. Henderson Plant General Manager
P. Mentel Manager Site Support Services (Acting)
C. Kamilaris Manager Nuclear Assessment
T. Pilo Fleet Coordinator - Emergency Preparedness
J. Overly Emergency Preparedness Supervisor
D. McGee Manager Shift Operations
M. Wallace Senior Specialist - Licensing