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Category:Letter type:NG
MONTHYEARNG-24-0004, 2023 Annual Radiological Environmental Operating Report2024-05-0808 May 2024 2023 Annual Radiological Environmental Operating Report NG-24-0003, Submittal of 2023 Annual Radioactive Material Release Report2024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Material Release Report NG-24-0001, 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update2024-03-0606 March 2024 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024 2023 Annual Exposure Report - Form 5s NG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021 Registration of Independent Spent Fuel Installation Storage Casks NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0030, Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-10-21021 October 2021 Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0028, Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 02021-07-30030 July 2021 Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 0 NG-21-0010, License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2021-06-28028 June 2021 License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme NG-21-0026, CFR 72.48 Report of Changes. Tests. and Experiments2021-06-16016 June 2021 CFR 72.48 Report of Changes. Tests. and Experiments NG-21-0011, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0404 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NG-21-0009, Report of Facility Changes. Tests and Experiments. and Commitment Changes2021-04-27027 April 2021 Report of Facility Changes. Tests and Experiments. and Commitment Changes NG-21-0021, Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements2021-04-22022 April 2021 Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements NG-21-0006, 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report2021-03-31031 March 2021 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-21-0005, NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 02021-03-29029 March 2021 NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 0 NG-20-0094, License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool2021-02-19019 February 2021 License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool NG-21-0004, Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report2021-02-0505 February 2021 Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report NG-20-0078, Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb)2021-01-13013 January 2021 Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb) NG-20-0101, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic2020-12-29029 December 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic NG-20-0099, Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-12-0101 December 2020 Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0093, Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-10-29029 October 2020 Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0090, Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center2020-10-12012 October 2020 Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center NG-20-0083, Registration of Independent Spent Fuel Installation Storage Casks2020-10-12012 October 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0069, Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2020-10-0707 October 2020 Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E NG-20-0082, Registration of Independent Spent Fuel Installation Storage Casks2020-09-28028 September 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0071, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic NG-20-0077, Registration of Independent Spent Fuel Installation Storage Casks2020-09-10010 September 2020 Registration of Independent Spent Fuel Installation Storage Casks 2024-05-08
[Table view] Category:Licensee Event Report (LER)
MONTHYEARNG-18-0040, LER 2018-001-00 for Duane Arnold Energy Center Regarding Loss of RPS Function During MSIV and TSV Channel Functional Testing Due to Use of a Test Box2018-04-0404 April 2018 LER 2018-001-00 for Duane Arnold Energy Center Regarding Loss of RPS Function During MSIV and TSV Channel Functional Testing Due to Use of a Test Box 05000331/LER-2017-0012017-03-27027 March 2017 Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage, LER 17-001-00 for Duane Arnold Energy Center Regarding Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage NG-17-0072, LER 17-001-00 for Duane Arnold Energy Center Regarding Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage2017-03-27027 March 2017 LER 17-001-00 for Duane Arnold Energy Center Regarding Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage 05000331/LER-2016-0032016-12-0606 December 2016 Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit, LER 16-003-00 for Duane Arnold Energy Center Regarding Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit 05000331/LER-2016-0022016-12-0606 December 2016 Unplanned RCIC Inoperability Results in Safety System Functional Failure, LER 16-002-00 for Duane Arnold Energy Center Regarding Unplanned RCIC Inoperability Results in Safety Functional Failure NG-16-0225, LER 16-003-00 for Duane Arnold Energy Center Regarding Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit2016-12-0606 December 2016 LER 16-003-00 for Duane Arnold Energy Center Regarding Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit NG-16-0226, LER 16-002-00 for Duane Arnold Energy Center Regarding Unplanned RCIC Inoperability Results in Safety Functional Failure2016-12-0606 December 2016 LER 16-002-00 for Duane Arnold Energy Center Regarding Unplanned RCIC Inoperability Results in Safety Functional Failure 05000331/LER-2016-0012016-08-18018 August 2016 Two Instances of Both Doors in Secondary Containment Airlock Opened Concurrently, LER 16-001-00 for Duane Arnold Energy Center Regarding Two Instances of Both Doors in Secondary Containment Airlock Opened Concurrently 05000331/LER-2015-0062016-02-18018 February 2016 HPCI and RCIC Condensate Storage Tank Suction Transfer Inoperable, LER 15-006-00 for Duane Arnold Regarding HPCI and RCIC Condensate Storage Tank Suction Transfer Inoperable 05000331/LER-2015-0022016-01-28028 January 2016 Unanalyzed Condition Due to Degraded Primary Containment Suppression Pool Coating, LER 15-002-01 for Duane Arnold Regarding Unanalyzed Condition Due to Degraded Primary Containment Suppression Pool Coating NG-15-0236, LERs 15-001-01 and 15-003-01 for Duane Arnold Regarding Both Doors in Secondary Containment Airlock Opened Concurrently2015-06-25025 June 2015 LERs 15-001-01 and 15-003-01 for Duane Arnold Regarding Both Doors in Secondary Containment Airlock Opened Concurrently NG-07-0355, LER 07-S01-00 for Duane Arnold Regarding Unauthorized Person Allowed Entry to Duane Arnold Energy Center Protected Area2007-05-0303 May 2007 LER 07-S01-00 for Duane Arnold Regarding Unauthorized Person Allowed Entry to Duane Arnold Energy Center Protected Area NG-03-0373, LER 03-S01-00, Duane Arnold Unattended Safeguards Information Outside of the Protected Area Caused by Personnel Error2003-05-15015 May 2003 LER 03-S01-00, Duane Arnold Unattended Safeguards Information Outside of the Protected Area Caused by Personnel Error 2018-04-04
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FPL Energy Duane Arnold, LLC 3277 DAEC Road Palo, Iowa 52324 FPL Enegy.
Duanie Aviidd Energy Center May 3, 2007 NG-07-0355 10 CFR 73.71 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 Licensee Event ReDort #2007-SO1-00 Please find attached the subject Licensee Event Report (LER) submitted in accordance with 10 CFR 73.71. This letter contains no new NRC commitments.
Gary Van Middlesworth Site Vice President, Duane Arnold Energy Center FPL Energy Duane Arnold, LLC cc: Administrator, Region III, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004) Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet LICENSEE EVENT REPORT (LER) e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC (See reverse for required number of may not conduct or sponsor, and a person is not required to respond to, the diqits/characters for each block) information collection.
- 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Duane Arnold Energy Center )5000 331 1 OF 3
- 4. TITLE Unauthorized Person Allowed Entry to Duane Arnold Energy Center Protected Area
- 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO. MONTHDAYYEAR 05000 0 FACILITY NAME DOCKET NUMBER 03 06 2007 2007 - S1 . 0 05 03 2007 05000
- 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 5 El 20.2201(b) [] 20.2203(a)(3)(i) [ 50.73(a)(2)(i)(C) [ 50.73(a)(2)(vii)
LI 20.2201(d) E] 20.2203(a)(3)(ii) [] 50.73(a)(2)(ii)(A) [ 50.73(a)(2)(viii)(A)
E] 20.2203(a)(1) Ej 20.2203(a)(4) [ 50.73(a)(2)(ii)(B) E] 50.73(a)(2)(viii)(B)
[] 20.2203(a)(2)(i) LI 50.36(c)(1)(i)(A) [ 50.73(a)(2)(iii) [ 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [] 20.2203(a)(2)(ii) [ 50.36(c)(1)(ii)(A) [] 50.73(a)(2)(iv)(A) [ 50.73(a)(2)(x)
E] 20.2203(a)(2)(iii) 0 50.36(c)(2) LI 50.73(a)(2)(v)(A) [ 73.71(a)(4) 0 E] 20.2203(a)(2)(iv) E] 50.46(a)(3)(ii) [] 50.73(a)(2)(v)(B) [ 73.71(a)(5)
[j 20.2203(a)(2)(v) Ej 50.73(a)(2)(i)(A) [] 50.73(a)(2)(v)(C) [ OTHER LI 20.2203(a)(2)(vi) [ 50.73(a)(2)(i)(B) [ 50.73(a)(2)(v)(D) Specify inAbstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Indude Aea Code)
Thomas R. Byrne - Senior Licensing Engineer (319) 851-7929
- 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CAUSE SYSTEM COMPONENT MANU- REPORTABLE CAUSE SYSTEM COMPONENT MANU- RE FACTURER TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR 0]YES (If yes, complete 15. EXPECTED SUBMISSION DATE) NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spacedtypewritten lines)
On March 6, 2007, a visitor flagged in the Personnel Access Data System (PADS) to be denied Protected Area (PA) access was allowed into the Duane Arnold Energy Center (DAEC) PA as an escorted visitor. The visitor was inside the protected area for 38 minutes and was escorted by an FPL Energy Duane Arnold employee for the duration of the time he was inside the DAEC PA. The visitor did not perform work on any plant equipment during this time. Subsequent to the discovery that this visitor should have been denied access, the visitor's access as an escorted visitor was revoked.
The cause of the event was personnel who performed the PADS check did not recognize that the visitor was prohibited access to the DAEC PA and consequently allowed escorted access. An error trap existed in that the denial statement in PADS, that was intended to indicate that the visitor should be denied access, was ambiguous and was misinterpreted by DAEC personnel performing the background check.
There were no actual safety consequences and no effect on public health and safety as a result of this event.
Neither this abstract nor the narrative portion of this report contains safeguards information.
This report is submitted pursuant to the requirements of 10 CFR 73.71 (a)(4).
NRC FORM 366 (6-2004) PRINTED ON RECYCLED PAPER
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
YEAR I SEQUENTIAL REVISION Duane Arnold Energy Center 05000331 NUMBER NUMBER 12007 -- S01 -- 00 2 of 3 TEXT (If more space is required,use additionalcopies of NRC Form 366A) (17)
I. Description of Event:
On March 6, 2007, a contractor reported to the Duane Arnold Energy Center (DAEC) to gain access to the DAEC Protected Area (PA) as an escorted visitor. While checking the visitor's status in the Personnel Access Data System (PADS), it was identified that the visitor should be denied access to the DAEC PA. An initial review by FPL Energy Duane Arnold determined that the individual had entered the DAEC PA on March 5, 2007 as an escorted visitor. The DAEC card reader history showed he was inside the PA for 38 minutes on March 5, 2007, and was escorted by an FPL Energy Duane Arnold employee for the entire time he was inside the DAEC PA. The visitor did not perform work on any plant equipment during this time.
PADS administration was contacted and verified that the visitor's social security number was run through the PADS system twice on the afternoon of March 5, 2007, and that a flag on the PADS screen stating "contact access" was present. Through interviews, it was identified that two separate DAEC security personnel had run the PADS check in accordance with a plant procedure but failed to identify the computer prompt to contact access.
There were no structures, systems, or components inoperable at the start of the event.
I1.Assessment of Safety Consequences:
Since the unauthorized visitor was escorted at all times and did not exhibit any symptoms of aberrant behavior during the 38 minute period of PA entry, there was little or no safety significance to this event.
Therefore, this event had no effect on the health or safety of the public.
Ill. Cause of Event:
Personnel who performed the PADS check did not recognize that the visitor was prohibited access to the DAEC PA and consequently allowed escorted access.
In reviewing the process for checking visitor's social security numbers through PADS, an error trap was identified in the training provided to security personnel to look for a denial statement in the PADS check screen. The denial statement in PADS for an individual to be denied access is "contact access." Personnel did not understand that this denial statement meant the visitor was prohibited access to the DAEC PA.
IV. Corrective Actions:
DAEC security personnel reviewed all personnel who had been flagged in the PADS identification check process from August 10, 2006 (date of completion of an FPL Energy Duane Arnold Nuclear Oversight PADS assessment) to the date of the incident and verified that all personnel who had received the "contact access" prompt were not permitted access to the PA. (ACE001 702)
DAEC security personnel contacted all FPL sites to brief them of the incident and developed a training presentation that was shared with the fleet to prevent reoccurrence at any of the FPL sites.
(ACE001702)
NRC FORM 366A (1-2001)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
YEAR SEQUENTIAL REVISION Duane Arnold Energy Center 05000331 1 NUMBER NUMBER 2007 -- S01 -- 00 3of3 TEXT (If more space is required,use additionalcopies of NRC Form 366A) (17)
A training presentation for all security personnel was developed to highlight what the PADS screens would look like for an individual who is not to be allowed access. Initial Security training has been modified to include this information. (ACE001702)
A formal request was made to the PADS administration to change the screen displayed to help highlight when unescorted access was denied at other facilities. PADS administration has since contacted the industry and provided the following information:
"A new color coded message scheme will be devised to provide the operator with a color-coded visual aid when operating the PADS Visitor ID Check process. The message text will be expanded to state "DO NOT ALLOW VISITOR TO ENTER CONTACT ACCESS." In addition, the operator will be required to acknowledge the "DO NOT ALLOW VISITOR TO ENTER CONTACT ACCESS" message by typing a six digit challenge code presented to the operator. The code must be entered by the operator in order to clear the screen and perform the next check." (ACE00Q1702)
V. Additional Information:
Previous Similar Occurrences:
A search for similar incidents revealed that Catawba has reported as a one-hour report a similar event on April 11, 2007 in which an entry of an unauthorized person (escorted visitor) into the protected area occurred. No other similar events were available in the INPO Operating Experience database.
A review of LERs at the DAEC over the last 3 years identified no LERs with similar events with similar causes.
EIIS System and Component Codes:
None Reporting Requirements:
This event is reportable per 10 CFR 73, Appendix G, Section I(b) which states that an actual entry of an unauthorized person into a protected area, material access area, controlled access area, vital area, or transport must be reported within one hour of discovery, followed by a written report within 60 days.
This report is being submitted under 10 CFR 73.71 (a)(4)
NRC FORM 366A (1-2001)