06-30-2010 | On April 29, (NS) 2010 the Unit 1 "A"-Train Containment Spray pump was declared inoperable upon discovery of. an oil leak on the Pump Motor Lower Bearing Sight-glass. The condition was entered into the site's corrective action program and a subsequent evaluation completed May 12, 2010, determined reasonable assurance of past operability could not be justified for a period of fourteen days. It was determined the event met 10 CFR50.73 reporting criteria as indicated in Section 11 (above).
Actions taken to correct the oil leakage prior to affecting the component's mission time were not adequate due to a failure to recognize or determine the existing condition correctly. Applicable procedures will be revised to provide additional information when making oil additions via oil sight glasses based on sight glass design and sealing characteristics, list the actions required in case low oil level is discovered, and provide additional information for components bound by mission time requirements. |
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BACKGROUND
The following information is provided to assist readers in understanding the event described in this LER. Applicable Energy Industry' Identification [EIIS] system and component codes are enclosed within brackets. McGuire unique system and component identifiers are contained within parentheses.
The Containment Spray System (NS) [BE] provides containment atmosphere cooling to limit post accident pressure and temperature in containment to less than the design values. Reduction of containment pressure and the iodine removal capability of the spray reduce the release of fission product radioactivity from containment to the environment, in the event of a Design Basis Accident (DBA).
Technical Specification (TS) 3.6.6 "Containment Spray. System" specifies that two NS [BE] trains shall be operable in MODES 1, 2, 3, and 4. TS 3.6.6 Condition A allows one NS [BE] train to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
TS 3.6.6 Condition B applies when an inoperable train exceeds the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) before required actions to restore the train to operable are complete. Condition B requires that the unit to be placed in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 in 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.
The pump motor oil sight glass.provides a visual means to monitor oil levels and in the case of the NS [BE] pump motor bearing, the sight glass provides a means of maintaining the oil level. The acceptable oil level isi,marked on the sight glass which is routinely monitored by station operators. For Systems, Structure, and Components (SSC) accessible during all plant conditions, oil addition is assured and provides reasonable assurance of operability. Conversely, oil addition to SSCs that cannot be accessed under all plant conditions may not provide a reasonable assurance of operability.
In these cases, the oil leak rate must not deplete the oil volume necessary to sustain SSC operability for the duration of the SSC mission time. The mission time is the duration of SSC operation that is credited in the design basis for the SSC to perform its specified safety function. The specified mission time for NS [BE] system is 30 days.
Repeated oil addition can indicate degradation requiring immediate repair and is entered into the site's corrective action program to evaluate the degraded condition and determine if additional action or maintenance is required.
The oil leaking from the NS [BE] pump motor was entered into the site's corrective action program on April 29, 2010. The 1A NS [BE] pump motor is not accessible for all postulated plant conditions and an engineering evaluation was required to determine how the past several oil additions affected the past operability of 1A NS [BE] pump motor.
Based upon measurements of the sight glass, amount of oil added, time period the oil was added, operating, environmental and radiological conditions, an engineering evaluation determined the leak rate would have resulted in exceeding the oil volume necessary to maintain 1A NS [BE] pump motor operability for the duration of the mission time. Reasonable assurance of past operability (i.e., ability to meet the 30 day specified mission time) could not be justified for a period of 14 days (April 15 - April 29, 2010).
At the time of the event, Unit 1 was operating in MODE .1 at 100% power.
During the 14 day period where operability was impacted, Unit 1 was in Modes 1-4 followinga refueling outage.
The unit's Technical Specification (TS) 3.6.6 allows for an inoperable NS was operated in a condition prohibited by TS and reportable under 10 CFR 50.73 (a)(2)(i)(B). Additionally, a surveillance .test pe'rformed during the fourteen day period rendered Unit 1 "B" Train NS [BE] pump inoperable resulting in two trains being simultaneous inoperable and is reported as an event or condition that could have prevented the fulfillment of a safety
EVENT DESCRIPTION
On April 29, 2010 at approximately 11:00 hours an oil leak of 24 drips per hour coming from the sight glass for the lower bearing oil reservoir on the "A" Train Containment Spray (NS) pump was declared inoperable, Technical Specification 3.6.6 was entered, and the condition was entered into the Technical Specification Action Item Log and documented in the site's corrective action program. The oil leak was subsequently corrected and the site exited TS 3.6.6 on April 29, 2010 at 16:16 hours.
An engineering evaluation, completed and approved on May 12, 2010, concluded that reasonable assurance of past operability (i.e., the oil leak rate could have exceeded the oil volume necessary to sustain pump operation for the 30 day mission time) could not be justified for a period of fourteen days (April 15 - April 29, 2010).
The duration that 1A NS Train was past inoperable would have exceeded the allowable completion time specified in the Unit's TS for approximately 11 days. Unit 1 was in a TS Mode of Applicability during this time period; therefore, Unit 1 had operated in a condition prohibited by the site's Technical Specifications and met the reporting criteria specified in 10 CFR 50.73 (a) (2) (i) (B). Additionally, the Unit 1 "B" Train NS was declared inoperable during this period (4/22/2010 @ 2014 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.66327e-4 months <br /> until 4/22/2010 @ 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br />) to perform surveillance. Therefore, this condition resulted in two NS Trains being simultaneously inoperable which, in addition to reporting as an operation prohibited by the unit's TS under 10 CFR 50.73 (a)(2)(i)(B)is reported as a condition that could have prevented fulfillment of a safety function per 50.73(a)(2)(v)(C).
The "discovery time" for the purpose of reporting this event is considered the time at which the engineering evaluation necessary to determine the impact to past operability was completed and approved (May 12, 2010).
CAUSAL FACTORS
The primary reason the oil level degraded to the point where the 1A NS pump motor's ability to meet the specified mission time was compromised was failure to recognize or determine the existing condition correctly. The low oil level was observed and assessed by several different people and disciplines. Therefore, individual assessments and conclusions were based on single data points rather than collective information. A root cause evaluation of the event indicated a process weakness regarding how each incidence of low oil level is tracked and trended and included several factors leading up to the organizations' failure to detect and correct the degraded condition before the mission time of a safety related component was adversely affected. Specifically:
- Maintenance procedures for oil sampling and oil additions are generic in nature and did not address the uniqueness of the sight glass design and the potential effect on the sight glass assembly configuration during maintenance activities.
- Insufficient program guidance and expectations to address mission time requirements (i.e. assurance of future operability under design basis event). Although, licensed operators have received training on Mission Time and its importance relative to operability, NUclear Equipment Operators were not included in the training population. Consequently, NEO response to low oil level indication was to replenish oil to ensure current operability and did not include any action to address the mission time of the SSC. or its future operability due to continuous oil additions.
- There was a lack of information for trending- equipment performance issues related to the frequency of oil addition to restore oil levels.
The requitement to submit oil addition data is required in the maintenance procedure for oil addition but the step did not specify hbw soon this needed to be accomplished. As a result, the information from completed procedures was sent in batches after all oil additions scheduled for the week were completed. Als6, the. enclosures did not provide the WR or WO number and dates for oil addition which could 1-ive facilitated trending.
CORRECTIVE ACTIONS
Immediate:
1. The 1A NS pump motor oil sight glass was repaired and pump motors using the same sight glass design were chetked to ensure correct oil levels and no leaks from sight glasses.
Subsequent:
1. Procedures controlling oil additions were placed on Technical Hold.
(Technical Hold ensures any additional guidance or restrictions are reviewed prior to executing the procedure).
Planned:
1. Revise applicable procedures to provide additional information on potential vulnerabilities when making oil additions via sight glasses based on sight glass design and sealing characteristics. Directions for proper tightening of applicable components on all sight glass designs will be included.
2.Revise Operations Management Procedure 5-5, Surveillance Monitoring, to list actions required when low oil level is identified. The actions will include guidance to detect possible leaks that may not be apparent based on the oil leak rate.
3.Revise Surveillance Rounds checklist, for components bound by mission time requirements, to list the mission time requirement and acceptable oil leak rate.
4.Revise applicable Mechanical Maintenance procedure steps to clarify the need to submit completed enclosures (oil additions) to engineering immediately.
SAFETY ANALYSIS
Duke Energy used a risk-informed approach to determine the risk significance associated with the Technical Specification violation associated with the oil leak on Unit 1 "A" Train NS pump motor.
The Conditional Core Damage Probability (CCDP) and the Conditional Large Early Release Probability (CLERP) of this event were evaluated by considering the following:
- The simplifying assumption that both the "A" NS [BE] Train and "B" NS [BE] Train are unavailable.
- The duration of the Limiting Condition for Operation non-compliance.
- The use of the average maintenance Probabilistic Risk Assessment (PRA) model to represent plant configuration, equipment unavailability, and maintenance activities during this violation.
The CCDP associated with this event was determined to be less than 1.0E 06. The CLERP associated with this event is non-limiting with respect to the CCDP and was determined to be less than 1.0E-7.
Furthermore, after the 1A NS [BE] pump was declared inoperable maintenance repaired the leak. There is currently no oil leaking from this motor and it is now operable.
Therefore, this event is considered to be of no significance to the health and safety of the public.
ADDITIONAL INFORMATION
a search of the McGuire Problem Investigation Process (PIP)d To determine if a recurring or similar event exists,d database was conducted for a time period covering 7 years prior to the date of this event. Based on Duke's definition of a recurring event, similar significant event with the same cause code, no recurring events were identified.
Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Performance Indicator Guideline", defines a Safety System Function Failure identical to 10 CFR 50.73(a) (2) (v) criteria. Consequently, reporting an event as an event or condition that could have prevented the fulfillment of the safety function of a structures, systems and components constitutes a Safety System Function Failure for the same basis used to deem the reporting criteria was met. This event is being reported under 10 CFR50.73 (a) (2) (v) because the NS [BE] "B" Train was declared inoperable to perform a channel test within the period of time the "A" Train NS [BE] was inoperable for an oil leak. This condition existed for a period of one hour and nine minutes; therefore, the safety system function failure existed for the same time. Although the condition unknowingly existed for a very short time, the safety evaluation assumed "B" Train NS [BE] was inoperable for the duration of time "A" Train NS [BE] was inoperable (14 days) to bound the significance of the condition. The safety analysis determined the condition to "be of no significance to the health and safety of the public.
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05000220/LER-2010-001 | Reactor Scram Due to Inadequate Post Maintenance Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000410/LER-2010-001 | Reactor Scram Due to Inadvertent Actuation of the Redundant Reactivity Control System During Maintenance | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000395/LER-2010-001 | Reactor Building Cooling Units Reduced Air Flow Rate Below Technical Specification Limits | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000382/LER-2010-001 | Spent Fuel Pool Cooling Single Failure | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000374/LER-2010-001 | High Pressure Core Spray System Declared Inoperable Due to Failed Room Ventilation Control Relay | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000373/LER-2010-001 | Unauthorized Individual Gained Access to the Protected Area. | | 05000370/LER-2010-001 | Loose connection in a panel board serving a Solid State Protection System Train concurrent with redundant train maintenance could have prevented fulfillment of a safety function. | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000261/LER-2010-001 | Emergency Diesel Generator Inoperable in Excess of Technical Specifications Allowed Completion Time | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000263/LER-2010-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000255/LER-2010-001 | Potential Loss of Safety Function Due to a Service Water Pump Shaft Coupling Failure | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000266/LER-2010-001 | Engineered Safety Features Steam Line Pressure Dynamics Modules Discovered Outside of Technical Specification Values | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000306/LER-2010-001 | Unit 2 Turbine Trip during Reactor Shutdown Resulting in a Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000305/LER-2010-001 | Safety Injection Pump Recirculation Line Isolation Results in Violation of Technical Specifications | | 05000298/LER-2010-001 | Cooper Nuclear Station 05000298 1 of 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000269/LER-2010-001 | Standby Shutdown Facility Letdown Line Orifice Strainer Blocked by Valve Gasket Material | 10 CFR 50.73(a)(2)(i)(b) | 05000282/LER-2010-001 | Unanalyzed Condition Due to Postulated High Energy Line Break On Cooling Water System | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000277/LER-2010-001 | Multiple Slow Control Rods Results in Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i) | 05000361/LER-2010-001 | Broken Manual Valve Prevents Timely Condensate Storage Tank Isolation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000483/LER-2010-001 | Emergency Core Cooling System MODE 4 Operating Practices Prohibited by current Technical Specification 3.5.3 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000498/LER-2010-001 | Unit Shutdown Required by Technical Specifications | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000316/LER-2010-001 | Valid Actuation of Auxiliary Feedwater System in Response to Valid Steam Generator Low-Low Levels | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000321/LER-2010-001 | Corrosion Induced Bonding Results in Safety Relief Valve Lift Setpoint Drift | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000336/LER-2010-001 | Millstone Power Station Unit 2 Reactor Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000413/LER-2010-001 | Technical Specification Violation Associated with Failure to Perform Offsite Circuit Verification | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000440/LER-2010-001 | Invalid Isolation Signal Results in Shutdown Cooling Interruption | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | 05000424/LER-2010-001 | Breaker Failure Results in I B Train Containment Cooling System Being Declared Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000416/LER-2010-001 | Automatic Reactor Scram On Decreasing Reactor Water Level Due To Inadvertent Reactor Feed Pump Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000249/LER-2010-001 | OPRM Power Supply Failure during Maintenance Results in Unit 3 Automatic Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000251/LER-2010-001 | Two Shutdown Bank Rods Were Dropped from Fully Withdrawn Position | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000261/LER-2010-002 | Plant Trip due to Electrical Fault | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000255/LER-2010-002 | Condition that Could Have Prevented the Fulfillment of a Safety Function | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000335/LER-2010-002 | Opened ECCS Boundary Door in Violation of Identified Compensatory Measures | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000334/LER-2010-002 | 270 Degree Circumferential Flaw Found on Residual Heat Removal System Drain Valve Socket Weld | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000316/LER-2010-002 | Containment Divider Barrier Seal Mounting Bolts Not Properly Installed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000250/LER-2010-002 | Fuel Transfer Pump Failure Renders 3B Emergency Diesel Generator Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000269/LER-2010-002 | Manual Reactor Trip due to 1A1 and 1A2 Reactor Coolant PumDHigh Vibration Indication | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000315/LER-2010-002 | Manual Auxiliary Feedwater Actuation in Response to Main Feedpump Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000271/LER-2010-002 | Inoperability of Main Steam Safety Relief Valves due to Degraded Thread Seals | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000277/LER-2010-002 | Improperly Fastened Rod Hanger Results in Inoperable Subsystem of Emergency Service Water | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000413/LER-2010-002 | Discovery of Reactor Coolant System Pressure Boundary Leak at Thermowell 1NCTW5850 Seal Weld. | | 05000282/LER-2010-002 | Postulated Flooding of Unit 1 Fuel Oil Transfer Pump Motor Starters Could Have Resulted In Reduced Fuel Oil Inventory | | 05000414/LER-2010-002 | Duke Energy Corporation Catawba Nuclear Station 4800 Concord Road York, SC 29745 803-701-4251 803-701-3221 fax December 15, 2010 U.S. Nuclear Regulatory Commission
Attention: Document Control Desk
Washington, D.C. 20555
Subject:�Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Unit 2
Docket No. 50-414
Licensee Event Report 414/2010-002
Pursuant to 10 CFR 50.73(a)(1) and (d), attached is Licensee Event Report 414/2010-002, Revision 0 entitled, "Technical Specification Violation Involving Mode Change with Inoperable Auxiliary Feedwater System Train Due to Closed Pump Discharge Valves". This report is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B). There are no regulatory commitments contained in this letter or its attachment. This event is considered to be of no significance with respect to the health and safety of the public. If there are any questions on this report, please contact L.J. Rudy at (803) 701-3084. Sincerely, faius4- A James R. Morris LJR/s Attachment www.duke-energy.corn (14 Document Control Desk Page 2 December 15, 2010 xc (with attachment): L.A. Reyes Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J.H. Thompson (addressee only) NRC Project Manager U.S. Nuclear Regulatory Commission Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto, Ill NRC Senior Resident Inspector Catawba Nuclear Station INPO Records Center 700 Galleria Place Atlanta, GA 30339-5957 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010) Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send commentsLICENSEE EVENT REPORT (LER) regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to infocollectssesource@nre.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used(See reverse for required number of to impose an information collection does not display a currently valid OMB control number, the NRCdigits/characters for each block) may not conduct or sponsor, and a person is not required to respond to, the info(mation collection. 1.. FACILITY NAME 2. DOCKET NUMBER I3. PAGE Catawba Nuclear Station, Unit 2 05000414 1 OF 7 4. TITLE Technical Specification Violation Involving Mode Change with Inoperable Auxiliary Feedwater System Train Due to Closed Pump Discharge ValvesD • | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000306/LER-2010-002 | Unit 2 Turbine Shutdown Due To the Loss of a Main Feed Water Pump That Resulted in a Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2010-002 | Piping Leak Results in Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000382/LER-2010-002 | Main Feedwater Isolation Valve B exceeded allowed outage time due to tubing connection failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000370/LER-2010-002 | ref Energy® REGIS T. REPKO Vice President McGuire Nuclear Station Duke Energy MGO1VP / 12700 Hagers Ferry Rd. Huntersville, NC 28078 980-875-4111 980-875-4809 fax regis.repko(Codu ke-energy.corn 10 CFR 50.73 May 10, 2011 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555 Subject: D Duke Energy Carolinas, LLC McGuire Nuclear Station, Unit 2 Docket Nos. 50-370 Licensee Event Report (LER) 370/2010-02, Supplement 1 Problem Investigation Process (PIP) M-10-05982 Pursuant to 10 CFR 50.73 Sections (a) (1) and (d), attached is Supplement 1 to Licensee Event Report 370/2010-02, regarding past inoperability of the Unit 2 "A" Train Nuclear Service Water System and satisfies the commitment to supplement the LER following completion of the root cause analysis This supplement to LER 370/2010-02 supersedes the LER previously submitted December 20, 2010. Completion of the root cause analysis has not affected the original reporting criteria which was completed in accordance with 10 CFR 50.73 (a) (2) (i) (B), an Operation Prohibited by Technical Specifications, and 10 CFR 50.73 (a) (2) (v) (B), any Event or Condition That Could Have Prevented Fulfillment of the Safety Function needed to remove residual heat. Additionally, the supplement did not affect the significance of the event which was considered to be of no significance with respect to the health and safety of the public. There are no regulatory commitments contained in this report. If questions arise regarding this LER, contact Rick Abbott at 980-875-4685. Very truly yours, Zi1:77 Regis T. Repko Attachment www. duke-energy. corn U.S. Nuclear Regulatory Commission May 10, 2011 Page 2 cc:�V. M. McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II
Marquis One Tower
245 Peachtree Center Ave., NC, Suite 1200
Atlanta, Georgia 30303-1257
Jon H. Thompson (Addressee Only)
Senior Project Manager (McGuire)
U.S. Nuclear Regulatory Commission
11555 Rockville Pike
Rockville, MD 20852-2738
J. B. Brady
Senior Resident Inspector
U.S. Nuclear Regulatory Commission
McGuire Nuclear Station
W. L. Cox Ill, Section Chief North Carolina Department of Environment and Natural Resources Division of Environmental Health Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB. NO 3150-0104 EXPIRES: 08/31/2013 (10-2010) Estimated burden per response to comply with this mandatory collection request: SO hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA/Privacy Section (T-5 F53), U.S. Nuclear Regulatory Commission. Washington, DC 20555-0001, or by Internet e-mail to info (See reverse for required number of collects resmirceOnrc.gov, and to the Desk Officer, Office of Information and Regulatory digits/characters for each block) Affairs, NEOB-10202, (3150-01041, Office of Management and Budget, Washington, DC 20503. If a means used to impose an 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. LICENSEE EVENT REPORT (LER) 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE McGuire Nuclear Station,2Unit 2 05000-212
0370 OF-7 4. TITLE Unit 2 Nuclear Service Water System "A" Train Past Inoperable due to
Failed Strainer Differential Pressure Instrument. | 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 | 05000369/LER-2010-002 | | | 05000456/LER-2010-002 | Limiting Condition for Operation Action Not Completed Within the Required Time | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000249/LER-2010-003 | Steam Leak Results in HPCI Inoperability | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000251/LER-2010-003 | Damaged Speed Sensor Caused the 4A Emergency Diesel Generator to be Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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