LER-2005-009, Re Firearm Discovered During Security Search Process |
| Event date: |
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| Report date: |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(vii)(A), Common Cause Inoperability
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(B) |
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| 3052005009R00 - NRC Website |
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text
Dominion Energy Kewaunee, Inc.
N490 Highway 42, Kewaunee, WI 54216-9511
~~DominionW 1 OCFR50.73 Dominion Energy Kewaunee, Inc.
Kewaunee Power Station N490, State Highway 42 Kewaunee, WI 54216-9510 July 15, 2005 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.:
KPS/LIC/MM Docket No.:
License No.:
05-446 RO 50-305 DPR-43
Dear Sirs:
Pursuant to 10 CFR 50.73, Dominion Energy Kewaunee, Inc., hereby submits Licensee Event Report applicable to Kewaunee Power Station.
the following Report No. 50-305/2005-009-00 This report has been reviewed by the Station Operating Review Committee and will be forwarded to the Management Safety Review Committee for its review.
Very truly yours, Kewaunee Power Station Attachment Commitments contained in this letter: NONE
iL
Serial No.05-446 Page 2 of 2 cc:
Mr. J. L. Caldwell Administrator Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. S. C. Burton NRC Senior Resident Inspector Kewaunee Power Station
Serial No.05-446 LER 2005-009-00 bc page 1 of 2 bc (hard copy distribution):
Mr. D. A. Christian Mr. W. R. Matthews Ms. L. N. Hartz Mr. E. S. Grecheck Ms. L. F. Barnett Licensing File Mr. M.C. Murph Records Management Records Management IN/2SW, Senior Vice President Nuclear MPS, Sr. Vice President Nuclear Operations IN/2SE, Vice President, Nuclear Engineering INI2SE, Vice President, Nuclear Support Services OJRP/20, Director Risk Services IN/2SE, Corp. Licensing OJRP/20 KPS*
GOV 02-54B-INGW*
bc (electronic distribution):
Mr. M. G. Gaffney Mr. J. A. Price Mr. J. M. Davis Mr. D. E. Jernigan Mr. K. K. Davison Mr. S. P. Sarver Mr. N. L. Lane Mr. K. B. Sloane Mr. T. J. Webb (eff. 7/25/05)
Mr. S. E. Scace Mr. G. T. Bischof Mr. W. Mathew Adams Mr. G. F. Winks Mr. M. J. Wilson Mr. H. Ashley Royal Mr. D. T. Llewellyn Ms. L. A. Armstrong Mr. W. W. Hunt Mr. J. A. Ruttar Mr. R. T. Schaefer Mr. K. Barnette Mr. G. 1. Harrington Mr. D. A. Sommers Mr. J. R. Harrell Mr. T. A. Brookmire Mr. L. J. Curfman Mr. G. D. Miller Mr. G. A. Novarro Mr. J. M. Surface Mr. D. M. Olson Mr. W. D. Corbin Mr. C. L. Funderburk Mr. R. M. Berryman INPO KPS, Site Vice President MPS, Site Vice President NAPS, Site Vice President SPS, Site Vice President KPS, Director Station Operations & Maintenance MPS, Director Station Operations & Maintenance NAPS, Director Station Operations & Maintenance SPS, Director Station Operations & Maintenance KPS, Director Station Safety and Licensing MPS, Director Station Safety and Licensing NAPS, Director Station Safety and Licensing SPS, Director Station Safety and Licensing KPS, Manager Nuclear Training MPS, Manager Nuclear Training NAPS, Manager Nuclear Training SPS, Manager Nuclear Training KPS, Manager Nuclear Site Engineering KPS, Manager Maintenance KPS, Manager Nuclear Operations KPS, Manager Nuclear Oversight KPS, Supv. Station Nuclear Safety KPS, Equipment Reliability and Pred. Analysis IN/2E, Supv. Licensing IN/3W, Supv. Nuclear Safety Analysis IN/3W, Supv. Fuel Performance Analysis IN/2NW, Nuclear Oversight IN/2SE, Licensing IN/3NW, Nuclear Programs IN/2SE, OE IN/2SE, MSRC Coordinator IN/3NW, Director Nuclear Engineering IN/2SE, Director Nuclear Lic. & Ops Support IN/2NW, Director Nuclear Oversight lerevents~inpo.orq
Serial No.05-446 LER 2005-009-00 bc page 2 of 2 Concurrence-See Regulatory Correspondence Review & Approval Record Verification of Accuracy
- 1. Security Event Report Number SE 05-02-17
- 2. Security Force Incident Report-incident Number S05-08
- 3. Kewanee County Sheriff's Department Statement Form (Dated 5/19/05)
- 4. Protected Area Visitor Log - FORM SIP 20.02-1
- 5. Procedure FP-PA-HU-01, Human Performance Program Action Plan/Commitments None.
Chanqes to the USAR or QA Topical Report None.
~,
,..-~'
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2007 (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.
LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the Records and FOlAPrivacyService Branch (r-5 F52), U.S. Nuclear RegulatoryCommission, Washington, DC20555-0001, orbyIntemet e-(See reverse for required number of mail to InfocollectsOnrc.gov, and to the Desk Officer, Office of Information and Regulatory (SeAffairs, NEOB-1 020Z (3150-0066), Office of Managemnent and Budget, Washington, DC 20503.
digits/characters for each block)
If a means used to Impose an Information collection does not display a currently valid OMB control number. the N RC may not conduct or sponsor, and a person Is not required to respond to, the Information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Kewaunee Power Station 05000305 1 of 3
TITLE (4)
Firearm Discovered During Security Search Process EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILmES INVOLVED (8) i FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER NO MO DAY YEAR 05 19 2005 2005 09 00 07 15 2005 FACILITYNAME DOCKETNUMBER OPERATiNG N
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR.: (Check all that apply) (11)
MODE (9) 20.2201 (b) 202203(a)(3)(ii) 50.73(a)(2)(ii)(B) l 50.73(a)(2)(ix)(A)
POWER 202201 (d) 20.2203(a)(4) 50.73(a)(2)(iif) 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(1) 50.36(o)(1)(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 202203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
X OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify In Abstract below or in
-:*-'i--_20.2203(a)(2)
(iv) 50.73(a) (2)(i)(A) 50.73(a) (2)(v)(D)_NCFrn36 20.2203(a)(2)(v)
_ 50.73(a)(2)(i)(B)
_ 50.73(a)(2)(vii) ;
N
= 20.2203(a)(2)(v) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)(A)
N F
366A 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(B)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Marv Jo Merholz - Licensing (920)388-8277 COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13)
MANU-REPORTABLE MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT FA CTURER TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR SUBMISSION YES (if yes, complete EXPECTED SUBMISSION DATE).
X No' DATE (15)
ABSTRACT On May 19, 2005, with the Kewaunee Power Station in refueling shutdown mode, a firearm was discovered during the security search process at the station's security entrance. The firearm was transported into the station's security area in a briefcase and was discovered during the x-ray unit search. The owner of the weapon was searched and detained in the shift captain's office until local law enforcement arrived. The weapon was placed in the station's security arms room. The cause of this event was poor worker practices. The owner of the weapon stated an awareness of the rules and regulations concerning the introduction of weapons at nuclear power stations and had forgot the weapon was located in the briefcase. Kewaunee Power Station management obtained the individual's resignation of employment. This event was shared with the Kewaunee Power Station security team and all station personnel. This event is reportable in accordance with 10 CFR 73.71 Appendix G Item I (d) as a condition of an actual or attempted introduction of contraband into a protected area. This occurrence has minimal safety significance and does not constitute a safety system functional failure.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME 1 DOCKET NUMBER 2 LER NUMBER (6)
PAGE 3 05000305 A)
SEQUENTIAL I REVISION Kewaunee Power Station 05000305 NUMBER NUMBER 2 of 3 l2005 09
-°° TEXT (It more space Is required, use additional copies of NRC Form 366A) (17)
EVENT DESCRIPTION
On May 19, 2005, at 0705 with the Kewaunee Power Station in refueling shutdown mode, a firearm was discovered during the security search process at the station's protected area access. A security watchperson discovered the firearm located in a briefcase as it passed through the security entrance x-ray. Upon discovery, the watchperson immediately pointed out the weapon to the security shift supervisor who was directly in the area conducting supervisory oversight during the morning ingress period. The briefcase containing the weapon was removed from the x-ray unit and controlled by the security shift supervisor.
At the time of the weapon discovery, the suspected owner of the briefcase was positioned at the entrance side of the x-ray unit placing additional items into the unit to be scanned. The suspected owner of the briefcase then passed through the metal detector and upon exiting was asked to identify the briefcase in question, at which time the individual claimed ownership of the briefcase. The individual agreed to a hands-on search of the briefcase.
Prior to conducting the hands-on search of the briefcase an armed security officer secured the owner of the briefcase, separating the owner from the briefcase in question. A search of the briefcase revealed a loaded revolver. Security personnel removed the owner of the briefcase from the search area and conducted a pat-down search of the individual. No additional contraband was discovered. The weapon was placed in the station's security arms room and the owner of the weapon was detained for the Local Law Enforcement Agency (LLEA). The LLEA arrived on site at approximately 0750.
Station management obtained the individual's resignation of employment from the Kewaunee Power Station.
The individual's name was placed on a site access review list that will no longer allow the individual past the station's security vehicle checkpoint. The LLEA completed their investigation and took possession of the weapon. At 0940 the individual was placed under arrest and transported to the LLEA office for final processing.
EVENT ANALYSIS
This event is reportable in accordance with 10 CFR 73.71 Appendix G Item I (d) as a condition of an actual or attempted introduction of contraband into a protected area.
SAFETY SIGNIFICANCE
This occurrence has minimal safety significance.
The individual was a new hire at the Kewaunee Power Station and was in the final processing stages for obtaining unescorted access. At no time during this event did the individual attempt to regain control of the briefcase containing the firearm. Prior to the date of this event and including the date of this event the individual had been provided access on site under visitor status. Before authorization of each site access, the individual was requested to read the "Protected Area Visitor and Vehicle Access" form which describes the policies and procedures for site access. During all of these instances the individual stated an understanding and agreement to comply with the station's site access policies. While on site the individual had been under the control of an escort at all times.U.S. NUCLEAR REGULATORY COMMISSION (1.2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME 1 DOCKET NUMBER 2 LER NUMBER 6 PAGE 3 IIYEARI SEQUENTIAL IREVISION Kewaunee Power Station 05000305 NUMBER I NUMBER 3o 12005 09 00 TEXT (If more space Is required, use aditionaf coples of NRC Fomri 366A) (17)
Interviews conducted with the employees who provided escorted access to the individual determined that the individual did not display any abnormal behavior. On May 19, 2005 a search was conducted of the individual's office area and nothing abnormal was found. In addition, a review of the video recordings in the x-ray search area was conducted for the prior entries of the individual. The review revealed that the briefcase used to transport the weapon was not brought on site previous to this event.
CAUSE
The cause of this event was poor worker practices. The owner of the weapon stated an awareness of the rules and regulations concerning the introduction of weapons at nuclear power stations and had forgot the weapon was located in the briefcase.
CORRECTIVE ACTIONS
- 1. Kewaunee Power Station management obtained the individual's resignation of employment.
- 2. This event was shared with the Kewaunee Power Station security team to ensure all security force members understand the event along with the actions that were taken by the officers involved.
- 3. The event was also shared with all site personnel as operating experience.
PREVIOUS SIMILAR EVENTS
None.
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| 05000305/LER-2005-001, Re Reactor Thermal Power Eight-Hour Average Limit Exceeded | Re Reactor Thermal Power Eight-Hour Average Limit Exceeded | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-002, Re Auxiliary Feedwater Pumps Assumed to Fall from Postulated Loss of Primary Water Source - Safe Shutdown and Accident Analysis Assumptions Not Assured - Inadequate Design of Pump Protective Equipment | Re Auxiliary Feedwater Pumps Assumed to Fall from Postulated Loss of Primary Water Source - Safe Shutdown and Accident Analysis Assumptions Not Assured - Inadequate Design of Pump Protective Equipment | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000305/LER-2005-003, Regarding Inadvertent Reactor Protection Trip While Shutdown - Caused by Procedure Adherence Deficiencies and Inadequate Shift Management Oversight | Regarding Inadvertent Reactor Protection Trip While Shutdown - Caused by Procedure Adherence Deficiencies and Inadequate Shift Management Oversight | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-004, Regarding Safe Shutdown Potentially Challenged by Unanalyzed Internal Flooding Events and Inadequate Design | Regarding Safe Shutdown Potentially Challenged by Unanalyzed Internal Flooding Events and Inadequate Design | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) | | 05000305/LER-2005-005, Re Emergency Diesel Generator Exhaust Ductwork Not Adequately Protected from Potential Tornado Winds & Missiles | Re Emergency Diesel Generator Exhaust Ductwork Not Adequately Protected from Potential Tornado Winds & Missiles | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-006, Re Auxiliary Feedwater Pumps Postulated to Fall Due to Air Ingestion Through Pump Packing | Re Auxiliary Feedwater Pumps Postulated to Fall Due to Air Ingestion Through Pump Packing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-007, Regarding Unanalyzed Condition: Design Deficiency - Component Cooling Water System Inoperable Due to Pump Run Out Conditions | Regarding Unanalyzed Condition: Design Deficiency - Component Cooling Water System Inoperable Due to Pump Run Out Conditions | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-008, Turbine-Driven Auxiliary Feedwater Pump Inoperable Due to Insufficient Net Positive Suction Head | Turbine-Driven Auxiliary Feedwater Pump Inoperable Due to Insufficient Net Positive Suction Head | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000305/LER-2005-009, Re Firearm Discovered During Security Search Process | Re Firearm Discovered During Security Search Process | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-010, Formal Withdrawal | Formal Withdrawal | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000305/LER-2005-011, Re the Setting of a Permissive (P-10) in the Power Range Channels of the Nuclear Instrumentation System Was Outside of Plant Technical Specification Requirements | Re the Setting of a Permissive (P-10) in the Power Range Channels of the Nuclear Instrumentation System Was Outside of Plant Technical Specification Requirements | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vi) 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-012, Re Residual Heat Removal Pump Run-Out Upon Loss of Instrument Air While Aligned for Sump Recirculation | Re Residual Heat Removal Pump Run-Out Upon Loss of Instrument Air While Aligned for Sump Recirculation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-012-01, For Kewaunee Power Station Re Residual Heat Removal Pump Run-Out Upon Loss of Instrument Air While Aligned for Sump Recirculation | For Kewaunee Power Station Re Residual Heat Removal Pump Run-Out Upon Loss of Instrument Air While Aligned for Sump Recirculation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-012-02, Regarding Residual Heat Removal Pump Run-Out Upon Loss of Instrument Air While Aligned for Sump Recirculation | Regarding Residual Heat Removal Pump Run-Out Upon Loss of Instrument Air While Aligned for Sump Recirculation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-013, Regarding the Throttle Valves to the Turbine Bearing Oil Coolers for the Turbine Driven AFW Pump Could Be Blocked by Debris | Regarding the Throttle Valves to the Turbine Bearing Oil Coolers for the Turbine Driven AFW Pump Could Be Blocked by Debris | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-014, Technical Specification LCO Not Entered for Diesel Generators Inoperable While in Refueling Shutdown | Technical Specification LCO Not Entered for Diesel Generators Inoperable While in Refueling Shutdown | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-014-01, Re Technical Specification LCO Not Entered for Diesel Generators Inoperable While in Refueling Shutdown | Re Technical Specification LCO Not Entered for Diesel Generators Inoperable While in Refueling Shutdown | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vi) 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-015, Kewuanee Both Trains of Component Cooling Water Inoperable During Shifting of Running Equipment | Kewuanee Both Trains of Component Cooling Water Inoperable During Shifting of Running Equipment | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000305/LER-2005-016-01, Re Automatic Reactor Trip Due to Main Feedwater Pump Motor Failure | Re Automatic Reactor Trip Due to Main Feedwater Pump Motor Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000305/LER-2005-016, Re Automatic Reactor Trip Due to Main Feedwater Pump Motor Failure | Re Automatic Reactor Trip Due to Main Feedwater Pump Motor Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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