IR 05000346/2008002: Difference between revisions
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{{#Wiki_filter:UNITED STATES | {{#Wiki_filter:UNITED STATES May 5, 2008 | ||
==SUBJECT:== | |||
DAVIS-BESSE NUCLEAR POWER STATION NRC INTEGRATED INSPECTION REPORT 05000346/2008002 | |||
Mr. | ==Dear Mr. Allen:== | ||
On March 31, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection findings which were discussed on April 14, 2008, with you and other members of your staff. Additionally, this inspection report documents special inspection activities associated with your compliance with the requirements of Confirmatory Order (EA-03-0214) and of Confirmatory Order (EA-07-0199). | |||
Davis-Besse Nuclear Power Station | |||
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. | |||
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. | |||
The | The report documents one NRC-identified finding and two self-revealing findings of very low safety significance (Green). Two of these findings were determined to involve violations of NRC requirements. Additionally, licensee-identified violations, which were determined to be of very low safety significance, are listed in this report. However, because of the very low safety significance and because the issues have been entered into your corrective action program, the NRC is treating the violations as non-cited violations (NCVs) in accordance with Section VI.A.1 of the NRC Enforcement Policy. | ||
If you contest the subject or severity of a Non-Cited Violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the Davis-Besse Nuclear Power Station. In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
Sincerely, | Sincerely, | ||
/RA/ Jamnes L. Cameron, Chief Projects Branch 6 Division of Reactor Projects Docket No. 50-346 License No. NPF-3 | /RA/ | ||
Jamnes L. Cameron, Chief Projects Branch 6 Division of Reactor Projects Docket No. 50-346 License No. NPF-3 Enclosure: Inspection Report 05000346/2008002 w/Attachment: Supplemental Information cc w/encl: The Honorable Dennis Kucinich J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer - FENOC Manager - Site Regulatory Compliance - FENOC D. Pace, Senior Vice President of Fleet Engineering - FENOC J. Rinckel, Vice President, Fleet Oversight - FENOC D. Jenkins, Attorney, FirstEnergy Corp. | |||
Director, Fleet Regulatory Affairs - FENOC Manager - Fleet Licensing - FENOC C. OClaire, Chief, Ohio Emergency Management Agency R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Lucas County Board of Commissioners President, Ottawa County Board of Commissioners | |||
=SUMMARY OF FINDINGS= | =SUMMARY OF FINDINGS= | ||
| Line 49: | Line 45: | ||
=REPORT DETAILS= | =REPORT DETAILS= | ||
.......................................................................................................................3 Summary of Plant Status...........................................................................................................3 | .......................................................................................................................3 Summary of Plant Status...........................................................................................................3 | ||
==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
| Line 108: | Line 104: | ||
==1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies== | ==1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies== | ||
{{IP sample|IP=IP 71114.05}} | {{IP sample|IP=IP 71114.05}} | ||
==RADIATION SAFETY== | ==RADIATION SAFETY== | ||
...................................................................................................22 2OS1 Access Control to Radiologically Significant Areas (71121.01).........................22 2OS2 As-Low-As-Is-Reasonably Achievable (ALARA) Planning And Controls (71121.02)...........................................................................................................26 2OS3 Radiation Monitoring Instrumentation and Protective Equipment (71121.03)....29 | ...................................................................................................22 2OS1 Access Control to Radiologically Significant Areas (71121.01) .........................22 2OS2 As-Low-As-Is-Reasonably Achievable (ALARA) Planning And Controls (71121.02) ...........................................................................................................26 2OS3 Radiation Monitoring Instrumentation and Protective Equipment (71121.03)....29 | ||
==OTHER ACTIVITIES== | ==OTHER ACTIVITIES== | ||
| Line 132: | Line 126: | ||
{{a|4OA6}} | {{a|4OA6}} | ||
==4OA6 Management Meetings......................................................................................49== | ==4OA6 Management Meetings ......................................................................................49== | ||
{{a|4OA7}} | {{a|4OA7}} | ||
==4OA7 Licensee-Identified Violations............................................................................49== | ==4OA7 Licensee-Identified Violations ............................................................................49== | ||
=SUPPLEMENTAL INFORMATION= | =SUPPLEMENTAL INFORMATION= | ||
| Line 143: | Line 137: | ||
==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | ||
........................................................1 | ........................................................1 | ||
==LIST OF DOCUMENTS REVIEWED== | ==LIST OF DOCUMENTS REVIEWED== | ||
.........................................................................................2 | .........................................................................................2 | ||
}} | }} | ||
Revision as of 17:05, 14 November 2019
| ML081270558 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/05/2008 |
| From: | Jamnes Cameron NRC/RGN-III/DRP/B6 |
| To: | Allen B FirstEnergy Nuclear Operating Co |
| References | |
| EA-03-0214, EA-07-0199, FOIA/PA-2010-0209 IR-08-002 | |
| Download: ML081270558 (73) | |
Text
UNITED STATES May 5, 2008
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION NRC INTEGRATED INSPECTION REPORT 05000346/2008002
Dear Mr. Allen:
On March 31, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection findings which were discussed on April 14, 2008, with you and other members of your staff. Additionally, this inspection report documents special inspection activities associated with your compliance with the requirements of Confirmatory Order (EA-03-0214) and of Confirmatory Order (EA-07-0199).
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
The report documents one NRC-identified finding and two self-revealing findings of very low safety significance (Green). Two of these findings were determined to involve violations of NRC requirements. Additionally, licensee-identified violations, which were determined to be of very low safety significance, are listed in this report. However, because of the very low safety significance and because the issues have been entered into your corrective action program, the NRC is treating the violations as non-cited violations (NCVs) in accordance with Section VI.A.1 of the NRC Enforcement Policy.
If you contest the subject or severity of a Non-Cited Violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the Davis-Besse Nuclear Power Station. In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Jamnes L. Cameron, Chief Projects Branch 6 Division of Reactor Projects Docket No. 50-346 License No. NPF-3 Enclosure: Inspection Report 05000346/2008002 w/Attachment: Supplemental Information cc w/encl: The Honorable Dennis Kucinich J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer - FENOC Manager - Site Regulatory Compliance - FENOC D. Pace, Senior Vice President of Fleet Engineering - FENOC J. Rinckel, Vice President, Fleet Oversight - FENOC D. Jenkins, Attorney, FirstEnergy Corp.
Director, Fleet Regulatory Affairs - FENOC Manager - Fleet Licensing - FENOC C. OClaire, Chief, Ohio Emergency Management Agency R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Lucas County Board of Commissioners President, Ottawa County Board of Commissioners
SUMMARY OF FINDINGS
...........................................................................................................1
REPORT DETAILS
.......................................................................................................................3 Summary of Plant Status...........................................................................................................3
REACTOR SAFETY
.......................................................................................................3
1R01 Adverse Weather Protection
.............................................................3
1R04 Equipment Alignment
........................................................................4
1R05 Fire Protection
...................................................................................5
1R08 Inservice Inspection Activities
...........................................................6
1R12 Maintenance Effectiveness
.............................................................13
1R13 Maintenance Risk Assessments and Emergent Work Control
........13
1R15 Operability Evaluations
....................................................................14
1R18 Permanent Plant Modifications
.......................................................15
1R19 Post Maintenance Testing (PMT)
....................................................16
1R20 Outage Activities
.............................................................................17
1R22 Surveillance Testing
........................................................................18
1EP2 Alert and Notification System Evaluation
.........................................20
1EP3 Emergency Response Organization (ERO) Augmentation Testing
.21
1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies
RADIATION SAFETY
...................................................................................................22 2OS1 Access Control to Radiologically Significant Areas (71121.01) .........................22 2OS2 As-Low-As-Is-Reasonably Achievable (ALARA) Planning And Controls (71121.02) ...........................................................................................................26 2OS3 Radiation Monitoring Instrumentation and Protective Equipment (71121.03)....29
OTHER ACTIVITIES
....................................................................................................32
4OA1 Performance Indicator Verification
.......................................................32
4OA2 Identification and Resolution of Problems
............................................34
4OA3 Followup of Events and Notices of Enforcement Discretion
.................39
4OA5 Other Activities...................................................................................................41
4OA6 Management Meetings ......................................................................................49
4OA7 Licensee-Identified Violations ............................................................................49
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
.....................................................................................................1
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
........................................................1
LIST OF DOCUMENTS REVIEWED
.........................................................................................2