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Category:Licensee Event Report (LER)
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Ginna Nuclear Power Plant, Regarding Unanalyzed Condition Due to Missing Barrier2013-05-31031 May 2013 For R.E. Ginna Nuclear Power Plant, Regarding Unanalyzed Condition Due to Missing Barrier 05000244/LER-2012-001, Regarding Automatic State of B Emergency Disesel Generator Caused by Loss of Offsite Circuit 767 Due to Wildlife2012-07-26026 July 2012 Regarding Automatic State of B Emergency Disesel Generator Caused by Loss of Offsite Circuit 767 Due to Wildlife 05000244/LER-2011-003, Regarding Reactor Trip Due to Failure of Tubine Lube Oil Piping2011-12-0202 December 2011 Regarding Reactor Trip Due to Failure of Tubine Lube Oil Piping 05000244/LER-2011-002, Regarding Train B Actuation Logic Circuit to Operate the B MSIV Was Not Operable2011-10-17017 October 2011 Regarding Train B Actuation Logic Circuit to Operate the B MSIV Was Not Operable 05000244/LER-2011-001, Re Unanalyzed Condition Due to Postulated Fire Causing a Station Blackout2011-10-0404 October 2011 Re Unanalyzed Condition Due to Postulated Fire Causing a Station Blackout ML0509600362004-12-17017 December 2004 Final Precursor Analysis - Ginna Grid Loop ML0429403762004-10-12012 October 2004 LER 04-S01-00 for R. E. Ginna Regarding Safeguards Event ML0202800752002-01-22022 January 2002 LER 01-S01-00 for R E Ginna Nuclear Plant Re Safeguards Event 05000244/LER-2078-007, For R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator1978-09-14014 September 1978 For R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator 05000244/LER-2078-006, R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom1978-08-0303 August 1978 R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom ML18142A8761978-08-0303 August 1978 LER 1978-006-00 for R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom 05000244/LER-2078-007-01, Bus 14 Breaker for C Safety Injection Pump1978-06-0606 June 1978 Bus 14 Breaker for C Safety Injection Pump ML18142A8771978-06-0606 June 1978 LER 1978-007-01 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump 05000244/LER-2078-005, For R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical1978-05-0202 May 1978 For R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical 05000244/LER-2078-004, For R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip1978-03-31031 March 1978 For R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip 05000244/LER-2078-002, R. E. Ginna, Power Range Low Range Trip Set Point Test1978-02-10010 February 1978 R. E. Ginna, Power Range Low Range Trip Set Point Test ML18142B2191978-02-0808 February 1978 LER 1978-003-00 for R.E. Ginna, B Steam Generator Tube Leak 05000244/LER-2078-003, B Steam Generator Tube Leak1978-02-0808 February 1978 B Steam Generator Tube Leak 05000244/LER-2077-008, B Steam Generator Tube Leak1977-07-18018 July 1977 B Steam Generator Tube Leak ML18142B2221977-07-18018 July 1977 LER 1977-008-00 for R.E. Ginna, B Steam Generator Tube Leak 05000244/LER-2077-006, C Charging Pump Varidrive on 6/19/19771977-07-0707 July 1977 C Charging Pump Varidrive on 6/19/1977 ML18142B2281977-06-0808 June 1977 Accumulation of Borated Water Near a Valve in Safety Injection System Piping 05000244/LER-2076-030-03, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak1977-05-27027 May 1977 Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak 05000244/LER-2077-003, Abnormal Degradation of Steam Generator Tubes1977-05-16016 May 1977 Abnormal Degradation of Steam Generator Tubes 05000244/LER-2077-007, Bus 14 Breaker for C Safety Injection Pump1977-03-31031 March 1977 Bus 14 Breaker for C Safety Injection Pump ML18142B2211977-03-31031 March 1977 LER 1977-007-00 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump ML18142B2381977-01-27027 January 1977 LER 1977-01-00 for R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump 05000244/LER-2077-001, R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump1977-01-27027 January 1977 R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump ML18142B2401977-01-12012 January 1977 LER 1976-030-00 for R.E. Ginna, a Mixed Bed Demineralizer Inlet Piping Leak 05000244/LER-2076-030, A Mixed Bed Demineralizer Inlet Piping Leak1977-01-12012 January 1977 A Mixed Bed Demineralizer Inlet Piping Leak ML18142B2431977-01-11011 January 1977 LER 1976-029-00 for R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition 05000244/LER-2076-029, R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition1977-01-11011 January 1977 R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition 05000244/LER-2076-028, R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work1977-01-11011 January 1977 R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work ML18142B2441977-01-0404 January 1977 LER 1976-027-00 for R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line 2024-03-07
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Joseph A. Widay 1503 Lake Road Plant Manager Ontario, New York 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC October 12, 2004 Mr. Robert L. Clark Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
Subject:
Reportable Safeguards Event LER 2004-S01, Safeguards Event R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Clark:
The attached Reportable Safeguards Event LER 2004-SOI is submitted in accordance with 10 CFR 73.71 and Section I(c) of Appendix G, Reportable Safeguards Events.
Very truly yours, J eph A. Widay
--,2E'- U lonI/4-h5
xc: Mr. Robert Clark (Mail Stop 0-8-C2)
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector Mr. James M. Petro Jr., Esquire Counsel Constellation Energy 750 East Pratt Street, 5th Floor Baltimore, MD 21202
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES 06/3012007 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 regarding burden estimate to the Records and FOIAPrivacy Service Branch (T-5 F52), U.S.
LICENSEE EVENT REPORT (LER) Nuclear Regulatory Commission. Washington. DC 20555-0001 or b( Internet e-mail to inocollects@nrc.gov, and to the Desk Officer, Office of Iniormation
- and Regulatory Affairs, NEOB-10202. (3150-0104), Office of Management and Budget. Washington. DC 20503. If a means used to Impose an information (See reverse for required number of collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the digits/characters for each block) information collection.
- 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE R. E. Ginna Nuclear Power Plant 05000 244 1 OF 3
- 4. TITLE Safeguards event
- 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED SEUNIA E ACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR S EQUENTIALREV MONTH DAY YEAR 05000 FACILITYNAME DOCKET NUMBER 08 13 2004 2004 - SOl - 00 10 12 2004 05000
- 9. OPEATING MODE , 11 THIS REPORT IS SUBMITUED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Checkal that apply)
El 20.2201(b) a 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) El 50.73(a)(2)(vii) 1 0 20.2201(d) El 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A)
El 20.2203(a)(1) 0 20.2203(a)(4) a 50.73(a)(2)(ii)(B) D 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) El 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) E 50.73(a)(2)(x) ol 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) E 73.71(a)(4)
El 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 100 0l 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) E 50.73(a)(2)(v)(C) E OTHER 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) E 50.73(a)(2)(v)(D) Specify InAbstract below
_____ ____ ____ ____or In NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER
-ACILITY NAME TELEPHONE NUMBER (Inctude Area Code)
Ronald C. Teed - Director Nuclear Security 1(585) 771-3232
- 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CAUSE l NNT MANU- REPORTABLE CAUSE SYSTEM COMPONENT MANU- REPORTABLE SYTMCMOETFACTURER TO EPIX jCMO FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR SUBMISSION o YES (Ifyes, complete 15. EXPECTED SUBMISSION DATE) E NO DATE ABSTRACT (Limit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)
On August 13, 2004, at approximately 0832 EDT, Ginna Nuclear Power Plant Security management was informed of the discovery of the mishandling of Safeguards Information. The address labels for two packages (one containing Safeguards Information and the other containing commercial documents) had been inadvertently switched during the shipping process at Ginna, and the two packages were mistakenly shipped to the wrong addressees. The Safeguards Information material was promptly resealed and packaged by the recipient who had mistakenly received the material, and was shipped back to Ginna. Upon receipt at Ginna, the Safeguards Information material was inventoried and all material was accounted for.
This event was determined to be reportable to the Nuclear Regulatory Commission in accordance with 10 CFR 73.71 and 10 CFR 73 Appendix G.
Corrective actions included debriefing the individual who had mistakenly received the Safeguards Information concerning prohibition of disclosure of Safeguards Information. The shipping process was changed at Ginna, such that shipping of all Safeguards Information will be processed only by designated Security personnel. Ginna personnel were notified of these changes by e-mail messages and messages attached to their security access badges.
NRC FORM 366 (6-2004) PRINTED ON RECYCLED PAPER
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1.2001)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE YEAR SEQUENTIAL I REVISION NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 2 OF 3 2004 -- S01 -- 00
- 17. NARRATIVE (If more space is required, use additional copies of NRC Form 366A)
- 1. PRE-E VENT PLANT CONDITIONS The plant was in Mode 1, at approximately 100% steady state reactor power.
- 11. DESCRIPTION OF EVENT Address labels for two packages (one containing Safeguards Information and the other containing commercial documents) had been inadvertently switched during the shipping process at Ginna Nuclear Power Plant (NPP), and the two packages were mistakenly shipped to the wrong addressees.
III. EVENT
SUMMARY
On August 11, 2004, a package containing Safeguards Information (SI) material was properly packaged for transmittal as SI from an engineer at Ginna NPP to an engineer at another power plant in New York, and was delivered to the Ginna Warehouse via normal shipping procedures for overnight shipping by that engineer (who is a person authorized for SI). Later that day, another package was delivered to the warehouse. This package contained a commercial document and a piece of cable, to be shipped to a company in North Carolina. Because of packaging requirements, the package containing SI material, as sent to the warehouse, was not different from any commercial package, and was ready for processing via the mail or overnight delivery service. The warehouse worker has no information as to whether he is processing SI or commercial information.
The warehouse worker judged that the packaging for the piece of cable was not robust, and should be packaged more securely. He then removed the internal tracking labels from both packages (the commercial package and the other package, which he did not know contained SI) and put both packages into more secure boxes. He then placed the external shipping labels on the packages, but had inadvertently switched the packages. Therefore, the label for the commercial information was placed on the package containing SI material, and vice-versa. The packages were then shipped via overnight delivery service later that day to their respective addressees.
On August 12, 2004, the individual in North Carolina received his expected package from Ginna NPP.
When he opened it, it did not appear to be the material he was expecting. He quickly scanned the pages (without reading the information) and verified that this material was not intended for him. He promptly resealed the materials, and had the package shipped back to Ginna NPP. Later that day, the engineer at the New York power plant opened his package and realized it was not the SI material that he had been expecting. He contacted the Ginna engineer. The Ginna engineer and warehouse worker investigated and determined that the shipping labels had been switched on the two packages the day before. They were not able to personally contact any individuals in North Carolina who may have received the package containing SI materials, but left messages for them to contact Ginna.
NRC FORM 366A (1 2001)
-'N\
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1.2001)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE yEAR SEQUENTIAL I REVISION NUMBER l NUMBER R.E. Ginna Nuclear Power Plant 05000244 - . 3 OF 3 2004 -- S01 - 00
- 17. NARRATIVE (ifmore space Is required, use additional copies of NRC Form 366A)
On August 13, 2004, the Ginna engineer informed his supervisor (who had not been on site the day before) of this event. At approximately 0832 EDT, Ginna NPP Security management was informed of the discovery of the mishandling of SI by the supervisor. This event was determined to be reportable to the Nuclear Regulatory Commission. The NRC Operations Center was notified of this event, per 10 CFR 73.71 and 10 CFR 73 Appendix G, at approximately 0925 EDT on August 13, 2004.
The initial security investigation consisted of interviews with all personnel that may have been involved.
Security personnel confirmed that the package containing SI had been shipped to the wrong address, and interviewed the individual who opened the package in North Carolina.
On August 13, 2004, at approximately 1025 EDT, the package containing SI material was received back at Ginna. The Ginna engineer inventoried the materials and confirmed that the document was complete.
IV. CORRECTIVE ACTION On August 13, 2004, at approximately 1320 EDT, the individual in North Carolina who had mistakenly received the package of SI material was interviewed by a Ginna Security Supervisor. The individual stated that he did not recall any details about the document he had opened, and that no one else had access to this material. He was informed of a directive prohibiting the unauthorized disclosure of SI, and agreed to this directive.
The shipping process was changed at Ginna. Procedures were changed to require that shipping of all SI will be processed only by designated Security personnel, to ensure proper packaging and shipping requirements are met. Ginna personnel were notified of this event and these changes by e-mail messages. A note was attached to each security access badge for personnel at Ginna NPP, informing them of this event and of the need to promptly report any compromise of SI, and announcing this change in the process for shipping SI.
The warehouse worker involved and the other warehouse workers were counseled by supervision following this incident.
NRC FORM 366A (1-2001)