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Category:Letter type:NRC
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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 2024-08-06
[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
William T. O'Connor, Jr.
\'ice President, Nuclear Generation Fermi 2 6400 North Dixie Jlhy., Newvport, Michigan 48166 Tel: 734-586-5201 Fax: 734-5864172 DTE Energy-10CFR73.71 November 8, 2004 NRC-04-0083 0801.26 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 (SER) No. 04-S02 Please find the enclosed Safeguards Event Report (SER) No. 04-S02, for a reportable event that occurred on October 11, 2004. This SER does not contain any new commitments.
Should you have any questions or require additional informnation, please contact Mr. Joseph H. Korte of my staff at (734) 586-1095.
Sincerely, cc: D. P. Beaulieu E. R. Duncan NRC Resident Office Region III Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission
-: 1.;. ;:.
. I NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: No. 3150-0104 Expires 6130/2007 (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 rearding burden estimate to the'Records and FOIA[Privacy Service Branch (-5 F52), U.S.
LIEN NTRE OR (ER EEEV NclarRegtoato m ss.Wahngton, DC 20555-0001, or by Internet e-mail to iNi OnCrC.g V.and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104). Offce of Management and (ereesfoofBudget. Washington. DC 20503. If a means use0t Impose an Information (See reverse for required number of 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 Information collection.
I. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Fermi 2 05000341 1 OF 3
- 4. TITLE Unescorted Access Revoked Upon Discovery of Adverse Information in Background Check
- 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 05000 10 11 2004 04 - S02 - 00 11 8 2004 FACILITY NAME DOCKET NUMBER j J...05000
- 9. OPERATING MODE 11. THIS REPORT SUBMITTED PURSUANT TO THE REQUIREMENTS OF I0 CFR§: (Check aft that apply) 10 20.2201(b) 0 20.2203(a)(3)i) El 50.73(a)(2)(1)(C) Cl 50.73(a)(2)(vii)
(
1 E 20.2201 (d) a 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) a 50.73(a)(2)(viii)(A) 1 20.2203(a)(1) Q20.2203(a)(4) Q50.73(a)(2)fii)(B) E] 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) El 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) J 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii) Q50.36(c)(11)(0)(A) 50.73(a)(2)(Iv)(A) [j 50.73(a)(2)(x) 0 20.2203(a)(2)(iii) 0 50.36(c)(2) E 50.73(a)(2)(v)(A) [D73.71(a)(4)I.
100 D 20.2203(a)(2)Ov) D 50.46(a)(3)(ii) D 50.73(a)(2)(v)(B) a] 73.71 (a)(5)
. 20.2203(a)(2)(v) D 50.73(a)(2)(1)(A) D 50.73(a)(2)(v)(C) D OTHER El 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) D 50.73(a)(2)(v)(D) Specify In abstract below or InNRC Form 366A
- 12. LICENSEE CONTACT FOR THS LER
'FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Joseph H. Korte, Manager - Nuclear Security (734) 586-1095
.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+/-FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR SUBMISSION U YES (I'uyes, complete 15. EXPECTED SUBMISSION DATE) NO DATE ABSTRACT (Limit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)
On October 6, 2004, a contractor employee was granted Reinstated Unescorted Access authorization to the protected and vital areas after the requirements of 10 CFR 73.56 were satisfied in accordance with NEI 03-01, "Industry Guideline for Nuclear Power Plant Access Authorization Programs," Revision 1.
On October 8, 2004, at approximately 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />, a review of the background investigation revealed that the contractor employee had failed to disclose adverse information in the background check process.
Upon discovery, the contractor employee's unescorted access was immediately suspended.
The adverse information was developed as the full background check was in progress subsequent to access authorization being granted on October 6, 2004. The employee was interviewed on October 11, 2004, about the adverse information. The employee admitted that the information received was factual but did not admit to intentionally falsifying or withholding information when requesting unescorted access. If this information was known at the time access authorization was being evaluated, the request for unescorted access would have been denied. The incident was reported to the NRC on October 11, 2004, in accordance with 10 CFR 73.71(b)(1).
NRC FORM 366 (6-2004)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE SEQUENTIAL REVISION
.YEAR NUMBER NUMBER Fermi2 05000341 2004 - S02l - 00 2 OF 3
- 17. NARRATIVE (if more space is required, use additional copies of NRC Form 366A)
Initial Plant Conditions:
Mode 1 Reactor Power 100 percent Description of the Event On October 6, 2004, after the requirements of 10 CFR 73.56 were satisfied in accordance with NEI 03-01, "Industry Guideline for Nuclear Power Plant Access Authorization Programs," Revision 1, Reinstated Unescorted Access authorization was granted to a contractor employee based on the personal history and employment information that was provided when requesting unescorted access to Fermi 2.
On October 7, 2004, as the full background check was in progress, information was developed from a former employer indicating that the contractor employee had recent illegal drug usage. The company involved was not related to the nuclear power industry, therefore, this adverse information did not appear on the Personnel Access Data Systems (PADS). The employee's unescorted access was suspended at approximately 1952 hours0.0226 days <br />0.542 hours <br />0.00323 weeks <br />7.42736e-4 months <br /> on October 8, 2004. The employee was interviewed at the next availability on site, October 11, 2004, at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />. The employee was questioned about the adverse information and the employee stated that the information received from the former employer was factual. The employee did not admit to intentionally falsifying the self disclosure information or withholding information when requesting unescorted access. Upon completion of the interview, the employee's unescorted access was revoked.
If the information was known at the time access authorization was being evaluated, the request for unescorted access would have been denied. Therefore, the incident was reported to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (Event #41112), in accordance with 10 CFR 73.71(b)(1).
Cause of the Event The cause of the event was the contractor employee failed to provide adverse information when requesting unescorted access to Fermi 2. All elements of the access authorization program described in the NRC approved Physical Security. Plan were correctly implemented by Detroit Edison.
Analysis of the Event This event had no adverse impact on the health and safety of the public. A transaction report was generated for the keycard activity from October 6, 2004, through October 8, 2004. The report revealed no record of access to the protected and vital areas of the plant. During the period of the employee's access, the contractor employee did not use the keycard. The contractor employee was not involved in any safety-related work during the time period unescorted access was authorized. There was no evidence of unusual behavior that would cause the contractor employee's supervisor to take any action under the Behavior Observation Program. This event did not affect or threaten plant safety systems. Local law enforcement assistance was not required, nor was there any media interest.
NRC FORM 366A (1-2001)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE SEQUENTIAL REVISION
-YEAR NUMBER NUMBER Fermi2 .05000341 2004 - S02 - 00 3 OF 3
- 17. NARRATIVE (Ifmore space Is required, use additional copies of NRC Form 366A)
Corrective Actions This event was entered into the Fermi 2 corrective action program. The contractor employee was escorted from the site and unescorted access was revoked. An investigation revealed that there was no programmatic or organizational weakness that contributed to this event. Therefore, there are no specific corrective actions to be taken to prevent a recurrence of this event.
Additional Information:
A. Failed Components: None B. Previous LERs on Similar Problems:
SER 2001-S01 describes a similar event where an individual was denied unescorted access.
NRC FORM 366A (1-2001)