05000364/LER-2004-002

LER-2004-002,
Docket Number
Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3642004002R00 - NRC Website
v • d • e

Westinghouse -- Pressurized Water Reactor Energy Industry Identification Codes are identified in the text as [XX]

Description of Event

The design function of HV3096A, CCW from Evaporator Packages and H2 Recombiners, is to automatically close on a low-low CCW surge tank level and to isolate the safety related portion of the system from the non-seismic, non-safety related portion of the system. On April 7, 2004, with Unit 2 in Mode 5, HV3096A would not open from the Main Control Board and was opened using its manual operator. A caution tag was placed on the valve documenting the abnormal position, and a work order was written for failure of the valve to open. In Mode 5, an actual LCO Action requirement did not then exist. Personnel who authorized placing the valve on the manual operator did not recognize that the condition made the on service train of CCW inoperable, and therefore did not generate an administrative LCO tracking sheet for the upcoming Mode 4 entry.

Work order review for Mode 4 entry did not detect the condition since the work order did not note that the valve had been placed on its manual operator and opened. Personnel reviewing tagging order status for Mode 4 entry erroneously determined that the valve status given on the tagging order would not constitute an LCO when Mode 4 was entered. Performance of this review is required by procedure, but the process for performing it is not formally defined.

Mode 4 was entered on April 8, 2004, at 1729. The condition was detected on April 8, 2004 at 2200 during the tagging order review for the upcoming Mode 3 entry. The valve was taken off its manual operator and closed, returning it to its fail safe condition.

Cause of Event

This event was due to cognitive personnel error. Personnel who authorized placing the valve on the manual operator did not recognize that the condition made the on service train of CCW inoperable, and therefore did not generate an administrative LCO tracking sheet for the upcoming Mode 4 entry.

Personnel reviewing tagging order status for Mode 4 entry erroneously determined that the valve status given on the tagging order would not constitute an LCO when Mode 4 was entered.

Safety Assessment The other train of CCW remained operable throughout this event.

The health and safety of the public were unaffected by this event.

This event does not represent a Safety System Functional Failure.

Corrective Action Personnel involved have been coached.

A Training Advisory Notice has been sent to Operations personnel informing them of the details of this event.

The Operations staff will be counseled concerning this event during the next training cycle by August 31, 2004.

A formal Mode change tagging order review process will be instituted by July 31, 2004.

Additional Information

The following LERs have been submitted in the past two years concerning Technical Specification violations:

3.4.12 Not Met.

Missile Barrier Not in Place.

Licensee Event Report

Docket Number

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 |

		Reporting criterion
05000348/LER-2004-001		10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000333/LER-2004-001	Inadvertent Actuation of ECCS and EDGs While in Refueling Mode	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000306/LER-2004-001		10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000315/LER-2004-001	Failure To Comply With Technical Specification 3 .7 .5 .1, Control Room Emergency Ventilation System
05000301/LER-2004-001		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000313/LER-2004-001		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000285/LER-2004-001	Failure To Perform A Leakage Test Due To Lack Of Understanding of Penetration Design	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000271/LER-2004-001	Main Steam Isolation Valve Leakage Exceeds a Technical Specification Leakage Rate Limit	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-2004-001		10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000318/LER-2004-001	. Reactor Trip Due to Low Steam Generator Water Level After Feed Pump Trip	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000289/LER-2004-001		10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000263/LER-2004-001
05000247/LER-2004-001	Manual Reactor Trip Due to Oscillating Feedwater Flow and Steam Generator Level with Flow Perturbations Caused by a Degraded Feed Water Regulating Valve	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation
05000244/LER-2004-001	Gaps in the Control Room Emergency Zone Boundary
05000255/LER-2004-001		10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000364/LER-2004-001		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000461/LER-2004-001	Clinton Power Station 05000461 1 OF 4
05000414/LER-2004-001	relPowere Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNO1VP York, SC 29745-9635 803 831 4251 803 831 3221 fax November 9, 2004 U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555-0001 SUBJECT: Duke Energy Corporation Catawba Nuclear Station Unit 2 Docket No. 50-414 Licensee Event Report 414/04-001 Revision 0 Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators Attached please find Licensee Event Report 414/04-001 Revision 0, entitled "Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in.Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators." This Licensee Event Report does not contain any regulatory commitments. Questions regarding this Licensee Event Report should be directed to R. D. Hart at (803) 831-3622. Sincerely, Dhiaa Jamil Attachment www.dukepower.corn 00- U.S. Nuclear Reguldhory Commission November 9, 2004 Page 2 XC: W.D. Travers U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie Senior Resident Inspector (CNS) U.S. Nuclear Regulatory Commission Catawba Nuclear Station S.E. Peters (addressee only) NRC Project Manager (CNS) U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 10-B3 11555 Rockville Pike Rockville, MD 20852-2738 NRC FORM 366� U.S. NUCLEAR REGULATORY APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)� COMMISSION Estimated burden per response to comply with this mandatory collection request 50 hours. Reported lessons learned are Incorporated Into the licensing process and fed back to Industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, WashinMon, DC 2055 LICENSEE EN/ENT REPORT (LER) 0001, or by Internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104). Office of Management(See reverse for required number of and Budget, Washington, DC 20503. If a means used to impose an Information col ectiond( inverse �for each block) does not display a currently valid OMB control number, the NRC may not conduct or sponsor. and a person Is not required to respond o. the Information collection. 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Catawba Nuclear Station, Unit 2 050- 00414 1 OF�6 4. TITLE Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators
05000368/LER-2004-001		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000423/LER-2004-001		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000334/LER-2004-001	Control Rod Shutdown Bank Anomaly Causes Entry into Technical Specification 3.0.3	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000413/LER-2004-001	Gas Accumulation in Centrifugal Charging Pump Suction Piping	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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000395/LER-2004-001	Reactor Trip Due to Valve Failure During Forced Shutdown	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000390/LER-2004-001	Automatic Reactor Trip Due to a Invalid Turbine Trip Signal (P-4)	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000369/LER-2004-001	Auxiliary Feedwater System in prohibited condition due to inadequate procedure.
05000454/LER-2004-001	Exelent Exelon Generation Company, LLCRwww.exeloncorp.com NuclearByron Station 4450 North German Church Road Byron, IL 61010-9794 October 17, 2004 LTR: BYRON 2004-0111 File: 2.01.0700 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Subject:RLicensee Event Report (LER) 454-2004-001-00, "Reactor Containment Fan Coolers Flow Rates Below Technical Specification Requirements Due to Inaccurate Flow Indication" Byron Station, Unit 1 Facility Operating License No. NPF-37 NRC Docket No. STN 50-454 Enclosed is an LER involving the August 17, 2004, event involving low flow conditions discovered in Unit 1 Reactor Containment Fan Coolers for a time period longer than allowed by the Technical Specifications. This event is reportable to the NRC in accordance with 10CFR 50.73 (a)(2)(i)(B), as a condition prohibited by Technical Specifications. Should you have any questions concerning this matter, please contact Mr. William Grundmann, Regulatory Assurance. Manager, at (815) 234-5441, extension 2800. Respectfully, Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station Attachment LER 454-2004-001-00 cc:RRegional Administrator, Region III, NRC NRC Senior Resident Inspector— Byron Station NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7.2001) COMMISSION Estimated burden per response to comply with this mandatory information collection request 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch (T.6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail toLICENSEE EVENT REPORT (LER) *I@ nrc.gov, and to the Desk Officer, Office of Informabon and Regulatory Affairs, NEOB:10202 (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose information 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 information collection. 1 rand ITV NAUP o natuerr An warn q par= . Byron Station, Unit 1 0500454 1 OF 5 4. Reactor Containment Fan Coolers Flow Rates Below Technical Specifications Requirements Due to Inaccurate Flow Indication	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000305/LER-2004-001		10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000336/LER-2004-001		10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000364/LER-2004-002		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000423/LER-2004-002		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000237/LER-2004-002	Dresden Nuclear Power Station Unit 2 05000237 1 of 5	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000261/LER-2004-002		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000244/LER-2004-002	Consolidated Rod Storage Canister Placed in Incorrect Storage Location
05000530/LER-2004-002	Main Turbine Control System Malfunction Results in Automatic Reactor Trip on Low DNBR	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000305/LER-2004-002
05000247/LER-2004-002	Manual Reactor Trip Due to Decreasing 23 Steam Generator Level Caused by Feedwater Regulating Valve Closure Due to a De-energized Solenoid Operated Valve from Wiring Failure	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000414/LER-2004-002	Manual Reactor Trip Initiated Due to Control Rods from Shutdown Bank D Dropping into the Core
05000251/LER-2004-002	AAA	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(b)
05000397/LER-2004-002		10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000346/LER-2004-002	Reactor Trip During Reactor Trip Breaker Testing Due To Fuse Failure	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000395/LER-2004-002	Emergency Diesel Generator Start and Load Due to Momentary Fault on Incoming Feed	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000269/LER-2004-002	eif Powere RON A. JONES Vice President A Duke Energy Company Oconee Nuclear Site Duke Power ONO1VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax September 9, 2004 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Subject: Oconee Nuclear Station Docket Nos. 50-269,-270, -287 Licensee Event Report 269/2004-02, Revision 1 Problem Investigation Process No.: 0-04-2808 Gentlemen: Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 269/2004-02, Revision 1, regarding a Main Steam Line Break mitigation design/analysis deficiency which could result in the main and startup feedwater control valves being technically inoperable for mitigation of some steam line break scenarios. This report is being submitted to supplement Revision 0 submitted July 6, 2004. At that time the root cause investigation and an analysis of the consequences of potentially exceeding the Environment Qualification (EQ) envelope curve were still in progress. This event is being reported in accordance with 10 CFR 50.73 (a)(2)(i)(B) as a condition prohibited by Technical Specifications, 50.73(a)(2)(ii)(B) as an Unanalyzed Condition, and 50.73(a)(2)(V)(D) as a potential loss of safety function for Accident Mitigation. This event is considered to be of no significance with respect to the health and safety of the public. www.dukepower.corn Document Control Desk Date: September 9, 2004 Page 2 Attachment: Licensee Event Report 269/2004-02, Revision 1 cc: Mr. William D. Travers Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, S. W., Suite 23T85 Atlanta, GA 30303 Mr. L. N. Olshan Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. M. C. Shannon NRC Senior Resident Inspector Oconee Nuclear Station INPO (via E-mail) NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7-2001) COMMISSION Estimated burden per response to comply with this mandatory information collection request: 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch (T-6 E6), U.S. Nuclear Regulatory Commission, Washington. DCLICENSEE EVENT REPORT (LER) 20555-0001, or by Internet e-mail to bpi @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 information collection doesdigits/characters for each block) not display a currently valid OMB control number, the NRC may not conduct or sponsor, and,1 nnmnn lc not rent Owl to tocnnni-I to the intnrmatinn rntlentinn 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Oconee Nuclear Station, Unit 1 050-81 OF 0269 11 4. TITLE Main Steam Line Break Mitigation Design/Analysis Deficiency	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000313/LER-2004-002		10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000271/LER-2004-002	Special Nuclear Material Inventory Location Discrepancy
05000285/LER-2004-002	Inoperable Diesel Generator for 28 Days Due to Blown Fuse During Shutdown	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000336/LER-2004-002		10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000311/LER-2004-002	Failure To Comply With Technical Specifications During Reactor Protection Instrument Calibration .	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000254/LER-2004-002	Quad Cities Nuclear Power Station Unit 1 05000254 1 of 4	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000263/LER-2004-002
05000302/LER-2004-002	Emergency Diesel Generator Inoperable Due To Fuel Oil Header Outlet Check Valve Leaking Past Seat	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
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05000364/LER-2004-002

Description of Event

Cause of Event

Additional Information

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