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Category:Letter type:NRC
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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] |
Text
Joseph H. Plona Site Vice President 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.5910 Fax: 734.586.4172 DTE Energy-
' 10 CFR 73.71 January 26, 2009 NRC-09-0004 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Safeguards Event Report No. 2008-S02, "Fitness for Duty (FFD)
Testing Results in Reinstated Access Authorization being Revoked" Pursuant to 10 CFR 73.7-1(a)(4), Detroit Edison is submitting the enclosed Safeguards Event Report (SER), No. 2008-S02. This SER documents a reportable event that occurred on December 4, 2008 involving the revocation of an employee's reinstated unescorted access upon the review of employee's drug testing results.
No new commitments are made in this letter.
Should you have any questions or require additional information, please contact Mr. Mark Findlay of my staff at (734) 586-1112.
Sincerely, cc: NRC Project Manager NRC Resident Office Director, Division of Nuclear Security Office of Nuclear Security and Incident Response Reactor Projects Chief, Branch 4, Region II Regional Administrator, Region II Supervisor, Electric Operators, Michigan Public Service Commission
i~<{~ ~:
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: No. 3150-0104 Expires (9/2007) 8/31/2010 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 lessons learned are incorporated into the LICENSEE EVENT REPORT (LER) licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch -5 F52), U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to lnfocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory/ Affairs, NEOB-10202 (3150-0104), Office of Management and (See reverse for required number of Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may digits/characters for each block) not conduct, or sponsor, and a person is not required to respond to, the I information collection.
- 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Fermi 2 05000341 1 OF 3
- 4. TITLE Fitness for Duty (FFD) Drug Testing Results in Reinstated Access Authorization being Revoked
- 5. ENT DATE 6. LER NUMBER 7. REP ORT DATE 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR I SEQUENTIAL j REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO 05000 12 04 08 2008 - S02 -00 01 26 09 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE 11. THIS REPORT SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all thatapply)
[J 20.2201 (b) [] 20.2203(a)(3i) 0 50.73(aY(2)1i)(C) [350.73(a)(2)(vii)
[1 20.2201 (d) 0 20.2203(a)3)(3i) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A)
[] 20.2203(a)(1) 20.2203(a)(4) 050.73(a)(2)(i)(B) 0 50.73(a)(2)(viii)(B)
[_ 20.2203(a)2)(i) 50.36(c)1l)(i)VA) 050.73(a)(2)(ili) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [320.2203(a)(2)ii) 50.36(c)1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x
[] 20.2203(a)(2)(iii) 05036(c)(2) 50.73(a)2)(2viA) El 73.71 (a)(4) 100 [020.2203(a)(2)(iv) 050.46(a)(3)(ii) [0 50.73(a)(2)(v) B) 073.71 (a)(5)
[020.2203(a)(2)(v) 050.73(a)(2)(i)(A) [] 50.73(a)(2)(v)(C) [0 OTHER
[020.2203(a)(2)(vi) 0] 50.73(a)(2)(i)(B) [050.73(a)(2)(v)(D) Specify in abstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THS LER FACILITY NAME FELEPHONE NUMBER (include Area Code)
Mark Findlay Manager, Nuclear Security Fermi 2 1734-586-1112
- 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CAUSE SYSTEM COMPONENT MANU- REPORTABLE CAUSE SYSTEM COMPONENT MANU- REPORTABLE FACTURER TO EPIX E FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR D YES (If yes, complete 15. EXPECTED SUBMISSION DATE) E NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spacedtypewritten lines)
On December 1, 2008 a contract employee was granted reinstated unescorted access authorization to the protected area after the requirements of 10 CFR 73.56 were satisfied in accordance with the Physical Security Plan and facility procedures. Unescorted access was granted pending results of a pre-access drug screen and reinstated access background check. The reinstated access background check was completed on December 1, 2008. On December 4, 2008 the results of the drug screen were determined to be positive for an illegal substance.
The employee's unescorted access was immediately suspended on December 4, 2008. A badge transaction report showed that the employee did not enter the protected area since being granted unescorted access. A review of the employee's safety-related work activity revealed no anomalies. The request for unescorted access would have been denied had this adverse information been known at the time access authorization was being evaluated. The incident was reported to the NRC on December 4, 2008 in accordance with 10 CFR 73.71.
NRC FORM 366 (9/2007)
1 NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (9-2007)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE YEAR SEQUENTIAL REVISION Fermi 2 05000341 NUMBER NUMBER 2 OF 3 2008 -- S02 -- 00
- 17. NARRATIVE (If more space is required, use additionalcopies of NRC Form 366.A)
Initial Plant Conditions:
Mode 1 Reactor Power 100%
Description of the Event On December 1, 2008 a contract employee requested reinstated unescorted access to the protected area. When inprocessing the employee completed a number of forms including a Self-Disclosure Information Form which asked if the employee "ever used, sold, or possessed illegal drugs or abused legal drugs?" The employee answered this question; "no". The request for reinstated unescorted access was dispositioned after the requirements of 10 CFR 73.56 were satisfied in accordance with the Physical Security Plan and facility procedures. There was no adverse information in the employee's background file that would have precluded granting unescorted access. On December 1, 2008 the employee was granted unescorted access pending completion of a pre-access drug screen and reinstated access background check. The reinstated access background check was completed on December 1, 2008 with no adverse information found. On December 4, 2008 the pre-access drug screen was determined to be positive for an illegal substance.
Upon discovery of the positive drug test result, the employee's unescorted access was immediately suspended. A badge transaction report was generated from December 1, 2008 through December 4, 2008. The report revealed the employee had not entered the protected area since being granted unescorted access. A review of the.
employee's safety-related work was completed on December 5, 2008 with no anomalies identified.
The request for unescorted access would have been denied had this adverse information been known at the time access authorization was being evaluated, The incident was reported within one hour to the NRC on December 4, 2008 in accordance with 10 CFR 73.71 (Event # 44695).
Cause of the Event The cause of the event was that the contract employee did not disclose illegal substance use during their request for unescorted access on December 1, 2008. All elements of the access authorization program described in the NRC-approved Physical Security Plan were appropriately implemented by Detroit Edison.
Analysis of the Event The event had no adverse impact on the health and safety of the public. A badge transaction report was generated for the keycard activity from December 1, 2008 through December 4, 2008. The report revealed that the employee did not enter the protected area. The employee's supervisor performed a review to determine if the employee had been involved in any safety-related work activity. The review was completed on December 5, 2008 and concluded that the employee did not perform any tasks on plant safety-related equipment. There was no evidence of unusual behavior that would cause the employee's supervisor to take any action under the NRC FORM 366A (9-2007)
1 NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (9-2007)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE YEAR ,SE'. UENTIAL I:,,IMBER R'vISION N'-71BER 3 O Fermi 2 05000341.- R -- 3 OF 3 Behavior Observation Program. This event did not threaten any plant safety systems. Local law enforcement assistance was not required, and there was no media interest.
Corrective Actions This event was entered into the Fermi 2 Corrective Action Program. The employee's unescorted access was revoked. The investigation revealed that adequate procedure guidance is in place for the elements of this event and there were no procedure violations by Nuclear Security personnel evaluating access authorization.
Additional Information:
A. Failed Components-None B. Previous Safeguards Event Reports (SERs) with Similar Conditions:
SER 2004-S02: Safeguards Event Report (SER) No. 04-S02 "Unescorted Access Revoked Upon Discovery of Adverse Information" SER 2008-SO 1: Safeguards Event Report No. 2008-SO 1, "Unescorted Access Revoked Upon Discovery of Adverse Information" These two SERs describe similar events where the employee did not disclose or did not fully disclose adverse information when requesting unescorted access during inprocessing. This event is the first one involving a confirmed positive drug screen received after granting reinstated unescorted access authorization.
NRC FORM 366A (9-2007)