Similar Documents at Fermi |
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Category:Letter type:NRC
MONTHYEARNRC-24-0007, Report of Changes to Quality Assurance Program for Radioactive Material Packages2024-01-12012 January 2024 Report of Changes to Quality Assurance Program for Radioactive Material Packages NRC-24-0002, Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122024-01-12012 January 2024 Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0079, Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 222023-12-14014 December 2023 Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 22 NRC-23-0077, Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan2023-12-0404 December 2023 Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan NRC-23-0073, Guarantee of Payment of Deferred Premiums2023-11-29029 November 2023 Guarantee of Payment of Deferred Premiums NRC-23-0071, Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-10-13013 October 2023 Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0062, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-10-12012 October 2023 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0068, Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-09-28028 September 2023 Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0064, Additional Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-09-11011 September 2023 Additional Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0057, Independent Spent Fuel Storage Installation Cask Registration2023-08-31031 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0054, Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30 20232023-08-31031 August 2023 Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30 2023 NRC-23-0056, Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval2023-08-31031 August 2023 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval NRC-23-0061, Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water..2023-08-30030 August 2023 Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water.. NRC-23-0059, Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0060, Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0053, Independent Spent Fuel Storage Installation Cask Registration2023-08-23023 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0050, Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-10010 August 2023 Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0048, Independent Spent Fuel Storage Installation Cask Registration2023-08-0101 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0049, Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-07-24024 July 2023 Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0043, Independent Spent Fuel Storage Installation, Cask Registration2023-06-27027 June 2023 Independent Spent Fuel Storage Installation, Cask Registration NRC-23-0020, License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance2023-06-13013 June 2023 License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance NRC-23-0039, Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-06-0606 June 2023 Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0030, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval2023-06-0505 June 2023 Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval NRC-23-0029, Snubber Program for the Fourth 10-Year Testing Interval2023-06-0505 June 2023 Snubber Program for the Fourth 10-Year Testing Interval NRC-23-0037, 56542-EN 56542 - Fermi2023-05-26026 May 2023 56542-EN 56542 - Fermi NRC-23-0031, Response to NRC Request from Audit of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources -Operating,' Emergency Diesel Generator Voltage and Frequency Surveillance Requirements2023-05-16016 May 2023 Response to NRC Request from Audit of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources -Operating,' Emergency Diesel Generator Voltage and Frequency Surveillance Requirements NRC-23-0002, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-05-0505 May 2023 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0010, License Amendment Request to Correct Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage2023-05-0505 May 2023 License Amendment Request to Correct Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage NRC-23-0017, Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report2023-04-28028 April 2023 Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report NRC-23-0025, Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2023-04-28028 April 2023 Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-23-0018, Annual Non-Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Non-Radiological Environmental Operating Report NRC-23-0024, Levels and Sources of Property Insurance Coverage2023-04-0303 April 2023 Levels and Sources of Property Insurance Coverage NRC-23-0021, ISFSI, Decommissioning Funding Plan Update2023-03-30030 March 2023 ISFSI, Decommissioning Funding Plan Update NRC-23-0016, Decommissioning Funding Status Report2023-03-30030 March 2023 Decommissioning Funding Status Report NRC-23-0015, Decommissioning Funding Status Report for Fermi 12023-03-30030 March 2023 Decommissioning Funding Status Report for Fermi 1 NRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023 License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis NRC-22-0026, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements2022-12-16016 December 2022 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements NRC-22-0051, DTE Electric Company - Guarantee of Payment of Deferred Premiums2022-11-29029 November 2022 DTE Electric Company - Guarantee of Payment of Deferred Premiums NRC-22-0052, Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 20222022-11-17017 November 2022 Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 2022 NRC-22-0046, Submittal of Biennial Review of the Fermi 1 Safety Analysis Report2022-11-14014 November 2022 Submittal of Biennial Review of the Fermi 1 Safety Analysis Report NRC-22-0041, Evacuation Time Estimate Report2022-10-0505 October 2022 Evacuation Time Estimate Report NRC-22-0033, Enrico Fermi Atomic Power Plant, Unit 1 - Annual Report for Period Ending June 30, 20222022-08-29029 August 2022 Enrico Fermi Atomic Power Plant, Unit 1 - Annual Report for Period Ending June 30, 2022 NRC-22-0030, Inservice Inspection Summary Report2022-08-10010 August 2022 Inservice Inspection Summary Report NRC-22-0023, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2022-08-0404 August 2022 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NRC-22-0022, Annual Non-Radiological Environmental Operating Report2022-04-29029 April 2022 Annual Non-Radiological Environmental Operating Report NRC-22-0021, Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report2022-04-29029 April 2022 Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report NRC-22-0020, Enrico Fermi Atomic Power Plant, Unit No. 1 & Fermi 2 Power Plant - 10 CFR 20.2206 Report of Individual Monitoring2022-04-28028 April 2022 Enrico Fermi Atomic Power Plant, Unit No. 1 & Fermi 2 Power Plant - 10 CFR 20.2206 Report of Individual Monitoring NRC-22-0003, Submittal of 2021 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2022-04-26026 April 2022 Submittal of 2021 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-22-0019, Submittal of the National Pollutant Discharge Elimination System Permit Application for Reissuance2022-04-0404 April 2022 Submittal of the National Pollutant Discharge Elimination System Permit Application for Reissuance NRC-22-0011, Enrico Fermi Atomic Power Plant, Unit No. 1 - Decommissioning Funding Status Report2022-03-31031 March 2022 Enrico Fermi Atomic Power Plant, Unit No. 1 - Decommissioning Funding Status Report 2024-01-12
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000341/LER-2017-0052017-11-0303 November 2017 Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function, LER 17-005-00 for Fermi 2 Regarding Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function 05000341/LER-2017-0042017-10-0909 October 2017 Inadequate Procedural Cuidance for Residual I feat Removal Complex Ventilation Systems Leads to Condition Prohibited by Technical Specifications and Loss if Safety Function, LER 17-004-00 for Fermi 2 Regarding Inadequate Procedural Guidance for Residual Heat Removal Complex Ventilation Systems Leads to Condition Prohibited by Technical Specifications and Loss of Safety Function 05000341/LER-2017-0032017-07-21021 July 2017 Division 2 Residual Heat Removal Service Water System (RHRSW) Inoperable Due to an Inoperable RHRSW Flow Control Valve, LER 17-003-00 for Fermi 2 Regarding Division 2 Residual Heat Removal Service Water System (RHRSW) Inoperable Due to an Inoperable RHRSW Flow Control Valve NRC-17-0040, (LER) SER 17-S01-00 for Fermi 2 Regarding Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility2017-05-15015 May 2017 (LER) SER 17-S01-00 for Fermi 2 Regarding Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility 05000341/LER-2017-0022017-03-16016 March 2017 High Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to be Inoperable, LER 17-002-00 for Fermi 2 Regarding High Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to be Inoperable 05000341/LER-2017-0012017-03-0606 March 2017 Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests due to Use of a Test Box, LER 17-001-00 for Fermi 2 Regarding Loss of Reactor Protection System Scram Function During the Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests due to Use of a Test Box 05000341/LER-2016-0012017-01-23023 January 2017 Turbine Stop Valve Closure and Turbine Control Valve Fast Closure Reactor Protection System Functions Considered Inoperable Due to Open Turbine Bypass Valves, LER 16-001-01 for Fermi 2 Regarding Turbine Stop Valve Closure and Turbine Control Valve Fast Closure Reactor Protection System Functions Considered Inoperable Due to Open Turbine Bypass Valves ML16138A3352016-05-17017 May 2016 ASP Screening Analysis - Reject Fermi Unit 2 (341-15-002) 05000341/LER-2016-0022016-03-22022 March 2016 Both Residual Heat Removal Low Pressure Coolant Injection Divisions Inoperable Due to Inoperable Injection Valve, LER 16-002-00 for Fermi 2, Regarding Both Residual Heat Removal Low Pressure Coolant Injection Divisions Inoperable Due to Inoperable Injection Valve NRC-13-0041, Submittal of Initial License Operator Examination2013-07-25025 July 2013 Submittal of Initial License Operator Examination NRC-09-0004, LER 08-S02-00 for Fermi 2 Regarding Fitness for Duty (FFD) Drug Testing Results in Reinstated Access Authorization Being Revoked2009-01-26026 January 2009 LER 08-S02-00 for Fermi 2 Regarding Fitness for Duty (FFD) Drug Testing Results in Reinstated Access Authorization Being Revoked NRC-08-0062, LER 08-S01-00 for Fermi 2 Regarding Unescorted Access Revoked Upon Discovery of Adverse Information2008-09-29029 September 2008 LER 08-S01-00 for Fermi 2 Regarding Unescorted Access Revoked Upon Discovery of Adverse Information ML0509505552004-12-17017 December 2004 Final Precursor Analysis - Fermi Grid Loop NRC-04-0083, LER 04-S02-00, Fermi 2 Unescorted Access Revoked Upon Discovery of Adverse Information in Background Check2004-11-0808 November 2004 LER 04-S02-00, Fermi 2 Unescorted Access Revoked Upon Discovery of Adverse Information in Background Check NRC-03-0020, LER 03-S01-00, Fermi 2, Unescorted Access Granted Prior to Verification of Fitness for Duty Drug Testing Results2003-03-0505 March 2003 LER 03-S01-00, Fermi 2, Unescorted Access Granted Prior to Verification of Fitness for Duty Drug Testing Results 2017-07-21
[Table view] |
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Keith J. Polson Site Vice President DTE Energy Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.4849 Fax: 734.586.4172 Email: keith.polsongdteenergy.com DTE Energy 10 CFR 73.71 .
May 15, 2017 NRC-17-0040 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Security Event Report (SER) No. 2017-SO1 Pursuant to 10 CFR 73.71(a)(4), DTE Electric Company (DTE) is submitting SER No.
2017-SO1, Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility.
No new commitments are being made in this SER.
Should you have any questions or require additional information, please contact Mr. Mark A. O'Connor, Manager -Nuclear Security, at (734) 586-1300.
Sincerely, Keit lo Site Vice President
Enclosure:
Security Event Report No. 2017-S01, Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility cc: Director, Division of Security Policy, Office of Nuclear Security and Incident Response.
NRC Project Manager NRC Resident Office Reactor Projects Chief, Branch 5, Region III Regional Administrator, Region III Michigan Public Service Commission Regulated Energy Division (kindschl@michigan.gov)
Enclosure to NRC-17-0040 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Security Event Report No. 2017-S01, Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017) Estimated burden per response to comply with thismandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned areincorporated intothelicensing process andfed back to industry.
LICENSEE ' EVENT LNuclear REPORT LER) Send comments regarding burden estimate totheInformation Services Branch (T-2 F43), U.S.
Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.
(See Page 2 for required number of digits/characters for each block) Resource@nrc.gov, andto theDesk Officer, Office of Information andRegulatory Affairs, NEOB-10202, (3150-0104), Office of Management andBudget, Washington, DC 20503. Ifa means (See NUREG-1022, R.3 for instruction and guidance for completing this form usedtoimpose aninformation collection does not display a currently valid OMB control number, http://www.nrc.gov/reading-rm/doc-collections/nureqs/staff/srl 022/r3/) the NRC may not conduct or sponsor, anda person isnot required torespond to, theinformation collection.
- 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Fermi 2 05000 1 OF 3
- 4. TITLE Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility
- 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITYNAME DOCKETNUMBER MONTH DAY NUMBER NO- 05000 FACILITY NAME -DOCKET NUMBER 03 23 2017 2017 - SO1 - 00 05 15 2017 05000
- 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
L 20.2201(b) [] 20.2203(a)(3)(i) [ 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 5 20.2201(d) Fi 20.2203(a)(3)(ii) Ei 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
E] 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)
- 10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) [ 73.71(a)(4) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 73.77(a)(1) 0 [j 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 73.77(a)(2)(i) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 73.77(a)(2)(ii) 50.73(a)(2)(i)(C) OTHER Specify in Abstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Area Code)
Cynthia M. Bomyea, Supervisor, Nuclear Security Staff (734) 586-5404
- 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CAUSE SYSTEM COMPONENT FACTURER REORT BLE CAUSE SYSTEM COMPONENT FACURER REORTBLE
- 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR YES (If yes, complete 15. EXPECTED SUBMISSION DATE) NO SUBMIION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On March 6, 2017, a supplemental employee was granted Unescorted Access (UA) at Fermi 2 without the knowledge that the supplemental employee was previously denied UA at DC Cook on March 1, 2017. On March 23, 2017, DC Cook contacted and informed Fermi 2 that the supplemental employee had been denied UA at DC Cook. It wasn't until the call was received from DC Cook that the Access Authorization group at Fermi 2 was aware that the individual in question had been denied UA.
The supplemental worker's UA was immediately suspended. The supplemental worker was interviewed regarding denial and UA was denied at Fermi 2 on March 23, 2017. If denial at DC Cook had been known at the time access authorization was being evaluated, the request for UA would have been denied. The incident was reported to the NRC on March 23, 2017 in accordance with 10 CFR 73.71.
A PADS Synopsis Form for validation is now initiated on the same day the background file case is reviewed by the Reviewing Official prior to granting unescorted access and unescorted access authorization. This was a process change and was incorporated into Fermi 2 procedure SEP-SEl-13. This will assure the most recent PADS Synopsis Form is reviewed and no unfavorable terminations have been issued prior to granting unescorted access.
NRC FORM 366 (04-20171
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported L S V(lessons learned are incorporated into the licensing process and fed back to industry. Send LICENSEE EVENT REPORT (LER) comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear CONTINUATION SHEET Regulatory Commission, Washington, DC 20555-0001, or by e-mail to infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management andBudget, Washington, DC 20503. Ifa means (See NUREG-1022, R.3 for instruction and guidance for completing this form used to impose an information collection does not display a currently valid OMB control number, the http://www.nrc.qov/reading-rm/doc-collections/nuregs/staff/srl022/r3/) NRC may not conduct or sponsor, anda person is not required to respond to, the information collection.
777
- 1. FACILITY NAME 2. DOCKET NUMBER 3. LER NUMBER YEAR SEQUENTIAL REV NUMBER NO.
Fermi 2 05000-2017 - O - 0 NARRATIVE Initial Plant Conditions:
Mode 5 Reactor Power 0%
Event
Description:
On March 23, 2017 at approximately 1112 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.23116e-4 months <br />, Fermi 2 Access Authorization was contacted by DC Cook's Access Authorization group requesting information on an individual who had been denied unescorted access at DC Cook and subsequently granted access at Fermi 2. Granting Unescorted Access (UA) to an individual in the "denied" state is contrary to 10CFR 73.56(h)(3). It was not until the call was received from DC Cook that the Access Authorization group at Fermi 2 was aware that the individual in question had been denied UA at DC Cook. Investigation concluded the event met the requirements for a 1-hour report to the NRC in accordance with 10CFR 73.71 and Generic Letter 91-03. UA was granted at Fermi 2 based on the individual's status as currently granted UA at DC Cook in the Personal Access Data System (PADS) on February 20, 2017. The individual's PADS Synopsis Form indicating he was currently granted UA at DC Cook was printed and placed in the background case file which is a standard practice for inprocessing preparations.
The remainder of the required background elements were then also compiled in the case file. Once all required information was compiled, access was granted on March 6, 2017 based on the PADS Synopsis form that had been generated on February 20, 2017. After the generation of the hard copy PADS Synopsis Form, information indicating a denial status was entered into the PADS database by DC Cook on March 1, 2017 unknown to Fermi 2 Access personnel.
Immediate Remedial Actions:
- 1. Individual was removed from the protected area at 1128 hours0.0131 days <br />0.313 hours <br />0.00187 weeks <br />4.29204e-4 months <br /> on March 23, 2017.
- 2. Unescorted access was denied on March 23, 2017.
- 3. Notifications were made to the Shift Manager and the NRC.
- 4. A review of all safety related work performed by this employee since March 6, 2017 was conducted by Nuclear Project Management and the Shift Manager verified that no safety related work or deficient work practices were performed that may impact the safe operation of the plant.
- 5. Fermi 2 Safeguards Event Report 17-036 and Condition Assessment Resolution Document (CARD) 17-22425 were generated to document this event.
Significant Safety Consequences and Implications:
The event had no adverse impact on the health and safety of the public. A transaction report was generated for the access badge activity. The employee did enter the protected area between the dates of March 6, 2017 and March 23, 2017. A review of safety-related work activity was completed by the worker's supervisor and no safety-related work was performed by the supplemental worker. This event did not threaten any plant safety systems. Local law enforcement assistance was not required, nor was there any media interest.
NRC FORM 366A (04-2017) Page 2 of 3
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported LCN*%E lessons learned are incorporated into the licensing process and fed back to industry. Send c a LICENSEE EVENT REPORT (LER) comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear CONTINUATION SHEET Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@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 (See NUREG-1022, R.3 for instruction and guidance for completing this form used to impose an information collection does not display a currently valid OMB control number, the http://www.nrc.gov/reading-rm/doc-collections/nureqs/staff/sr1022/r3/) NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME 2. DOCKET NUMBER 3. LER NUMBER YEAR SEQUENTIAL REV Fermi 2 05000- NUMBER NO.
341 [07 SO1 - 00 NARRATIVE Apparent / Contributing Cause:
All elements of the case file review are conducted manually, therefore, any documentation that can be produced prior to the inprocessing date was placed in the review folder and checked off as complete. Once all elements are complete, the case file was ready for review. This process of checking PADS prior to arrival and placing that information in the case file review folder allowed a time lapse between verifying no unfavorable terminations were issued and granting unescorted access.
Corrective Actions:
A PADS Synopsis Form for validation is now initiated on the same day the background file case is reviewed by the Reviewing Official prior to granting unescorted access and unescorted access authorization. This was a process change and was incorporated into Fermi 2 procedure SEP-SE1-13. This will assure the most recent PADS Synopsis Form is reviewed and no unfavorable terminations have been issued prior to granting unescorted access.
Additional Information:
Type of Security Force: Proprietary & Contract Previous Safeguards Event Reports with Similar Conditions: Review of the SER indicate no similar events.
NRC FORM 366A (04-2017) Page 3 of 3