05000220/FIN-2014005-01: Difference between revisions

Finding

Title

Incomplete and Inaccurate Medical Information Provided by Exelon Which Impacted Issuance of Initial and Renewal Licenses

Description

Exelon Generation Company, LLC (Exelon) identified two AVs: (1) An AV of Title 10 of the Code of Federal Regulations (10 CFR) 50.9, Completeness and Accuracy of Information; and (2) An AV of 10 CFR 50.74, Notification of Change in Operator or Senior Operator Status. Specifically, during an internal audit in July 2014, Exelon identified that between September 2002 and February 2012, NMPNS staff submitted certified copies of an NRC reactor operator and/or senior operator license applications for seven applicants that did not specify that the applicants required a restriction in order to maintain medical qualifications. The NRC issued the reactor operator and senior operator initial and renewed licenses for the seven applicants, but without the necessary medical restrictions (AV #1). From June 2002 through August 2014, Exelon had numerous additional opportunities to identify these potentially disqualifying medical conditions and that license conditions were required during the biennial licensed operator requalification program reviews and medical examinations. On September 25, 2014, a period that exceeded 30 days from when the conditions were identified, the facility notified the NRC of these medical conditions via a letter requesting amendment to the seven operators licenses to include the appropriate restrictions (AV #2). The NRC issued the license amendment with the new restrictions. The NRC inspectors also identified an additional example of both AVs which had not been reported by Exelon to the NRC in the September 25, 2014 letter. On November 5, 2014, Exelon requested termination of the license for that operator. This issue was entered into Exelons corrective action program (CAP) The inspectors determined that Exelons failure to provide complete and accurate information to the NRC in the reactor operator and senior operator license applications and to notify the NRC of a change in a reactor operator or senior operators status for a condition which was known by Exelon were performance deficiencies that were within their ability to foresee and correct and should have been prevented. The inspectors determined that traditional enforcement applies, as the issue affected the NRCs ability to perform its regulatory function. Namely, the NRC requires Exelon to ensure all licensed operators meet the medical conditions of their licenses. If, during the term of the individual operator license, an operator develops a permanent physical or mental disability that causes the operator to fail to meet the requirements of 10 CFR 55.21, Medical Examination, the licensee shall notify the NRC within 30 days of learning of the diagnosis, in accordance with 10 CFR 50.74(c). Additionally, the NRC issued reactor operator and senior operator licenses to the applicants based on information that was not complete and accurate in all material aspects. The performance deficiencies were screened against the Reactor Oversight Process per the guidance of IMC 0612, Appendix B, Issue Screening. No associated Reactor Oversight Process finding was identified and no cross-cutting aspect was assigned. These issues constitute AVs in accordance with the NRCs Enforcement Policy, and their final significance will be dispositioned in separate future correspondence. (Section 1R11)

01
Site:	Nine Mile Point
Report	IR 05000220/2014005 Section 1R11
Date counted	Dec 31, 2014 (2014Q4)
Type:	TEV: Severity level III
cornerstone	Mitigating Systems
Identified by:	NRC identified
Inspection Procedure:	IP 71111.11
Inspectors (proximate)	A Dimitriadis A Rosebrook B Sienel C Franklin E Miller G Stock J Deboer K Kolaczyk S Horvitz T Fisha Rosebrook B Sienel C Graves D Schroeder E Andrews E Burket E Miller G Stock J D'Antonio K Kolaczyk M Modes T Dunn W Cookm Modes T Dunn W Cook A Rosebrook B Sienel C Graves D Schroeder E Andrews E Burket E Miller G Stock J D 'Antonio K Kolaczy
Violation of:	10 CFR 50.74 10 CFR 50.9 10 CFR 55.21 License Condition
INPO aspect
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v • d • e

Finding - Nine Mile Point - IR 05000220/2014005

1(0)2(2)3(4)4(1)5(4)6(0)7(4)201(0)202(0)403(0)404(5)301(0)

IR 05000220/2014005: 1 2 3 4

Finding List (Nine Mile Point) @ 2014Q4

CCA Matrix: 2014Q4

	Q	CCA	Title
05000220/FIN-2014002-01	2014Q1		Inadequate Design Control Measures Employed During Control Room HVAC Modification
05000410/FIN-2014002-02	2014Q1	H.14	Invalid Low Reactor Water Level Results in Unit 2 Automatic Reactor Scram
05000220/FIN-2014404-01	2014Q2		Security
05000220/FIN-2014404-02	2014Q2		Security
05000220/FIN-2014404-03	2014Q2		Security
05000410/FIN-2014003-01	2014Q2		Inadequate Surveillance Testing of Reactor Core Isolation Cooling during 165 psig Reactor Pressure Test for Surveillance Requirement 3.5.3.4
05000220/FIN-2014003-02	2014Q2	P.3	Failure to Correct a Significant Condition Adverse to Quality in a Timely Manner
05000410/FIN-2014003-03	2014Q2	H.11	Loss of Spent Fuel Cooling Pump due to Inadequate Procedures
05000410/FIN-2014003-04	2014Q2		Failure to Identify Single-Point Vulnerabilities Results in a Manual Reactor Scram
05000410/FIN-2014004-01	2014Q3	H.1	Loss of Secondary Containment due to Loss of Auxiliary Boiler System
05000220/FIN-2014005-02	2014Q4		Failure to Make Timely Reports of Changes in Licensed Operator Medical Status Which Impacted Issuance of Initial and Renewal Licenses
05000410/FIN-2014007-01	2014Q4	P.5	Deficient Design Control of NMP Unit 1 Electrical Calculations to Evaluate Minimum Voltages to Class 1E Accident Initiated Motors and MOVs during a Design Basis Event
05000410/FIN-2014005-04	2014Q4		Assessment of UPS3B Failure Which Resulted in a Reactor Scram
05000220/FIN-2014005-01	2014Q4		Incomplete and Inaccurate Medical Information Provided by Exelon Which Impacted Issuance of Initial and Renewal Licenses
05000410/FIN-2014005-03	2014Q4	H.12	Missed Surveillance Test of Alternate Decay Heat Removal Secondary Containment Isolation Valves
05000220/FIN-2014007-03	2014Q4		Deficient Design Control of Protective Device Sizing for Unit 1 Core Spray Injection Motor-Operated Valves
05000220/FIN-2014007-02	2014Q4	P.5	Deficient Design Control of NMP Unit 1 Electrical Protection Design to Ensure Survivability of Safety-Related Loads

Self-Identified List (Nine Mile Point)

	Q	Title
05000220/FIN-2014404-04	2014Q2	Licensee-Identified Violation
05000220/FIN-2014404-05	2014Q2	Licensee-Identified Violation
05000220/FIN-2014007-04	2014Q4	Licensee-Identified Violation

[Nine Mile Point Findings full list]

@@ Line 12: / Line 12: @@
 | identified by = NRC
 | Inspection procedure = IP 71111.11
-| Inspector = A Dimitriadis, A Rosebrook, B Sienel, C Franklin, E Miller, G Stock, J Deboer, K Kolaczyk, S Horvitz, T Fishm, Modes T, Dunn W, Cook A, Rosebrook B, Sienel C, Graves D, Schroeder E, Andrews E, Burket E, Miller G, Stock J, D'Antonio K, Kolaczyka Rosebrook, B Sienel, C Graves, D Schroeder, E Andrews, E Burket, E Miller, G Stock, J D,'Antonio K, Kolaczyk M, Modes T, Dunn W, Coo
+| Inspector = A Dimitriadis, A Rosebrook, B Sienel, C Franklin, E Miller, G Stock, J Deboer, K Kolaczyk, S Horvitz, T Fisha, Rosebrook B, Sienel C, Graves D, Schroeder E, Andrews E, Burket E, Miller G, Stock J, D'Antonio K, Kolaczyk M, Modes T, Dunn W, Cookm Modes, T Dunn, W Cook, A Rosebrook, B Sienel, C Graves, D Schroeder, E Andrews, E Burket, E Miller, G Stock, J D,'Antonio K, Kolaczy
 | CCA = N/A for ROP
 | INPO aspect =

05000220/FIN-2014005-01: Difference between revisions

Revision as of 20:04, 20 February 2018

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