12-21-2006 | On October 26, 2006, with the plant shutdown for a refueling outage, and 29 days after a charcoal adsorber sample was taken from a Spent Fuel Pool Charcoal Adsorber System filter for penetration testing per Technical Specification (TS) surveillance SR 3.7.10.3 and specification 5.5.10, the methyl iodide penetration level of the charcoal sample was determined to be unacceptable.
Movement of irradiated fuel that had decayed Building commencing on October 15, 2006. As a result of the unsatisfactory test result, TS 3.7.10 was not met. Therefore, this occurrence is considered reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the Ginna Technical Specifications.
The cause of this event was due to incorrect test parameters being previously supplied to the vendor that performed the methyl iodide penetration testing and a delay in obtaining the test results.
Corrective action to address the condition is outlined in Section V.
Subsequent analysis has concluded that a fuel handling accident with degraded charcoal filtration would not have resulted in applicable regulatory limits being exceeded; therefore, this event had no impact on the health and safety of the public. |
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I. PRE-EVENT PLANT CONDITIONS:
At the time the condition was identified, the plant was in Mode 5 at 0% rated thermal power, following a refueling of the reactor.
II. DESCRIPTION OF EVENT:
EVENT:
Technical Specification LCO 3.7.10 requires that the Auxiliary Building Ventilation System (ABVS), of which the Spent Fuel Pool Charcoal Adsorber System is part of, be operable during movement of irradiated fuel assemblies in the Auxiliary Building when one or more fuel assemblies in the Auxiliary Building has decayed On September 27, 2006, a charcoal sample was taken from a Spent Fuel Pool Charcoal Adsorber System filter for testing per Technical Specification (TS) surveillance SR 3.7.10.3 and specification 5.5.10, prior to refueling activities. On October 11, 2006, the sample was sent to NUCON's laboratory for methyl iodine removal efficiency testing. On October 15, 2006, movement of irradiated fuel that had decayed Auxiliary Building. On October 26, 2006, NUCON notified Ginna that the efficiency of the charcoal sample was 64.3%, which was less than the Ginna Technical Specification limit of > 85.5%. As such, the Spent Fuel Pool Charcoal Adsorber System was not operable per Technical Specification LCO 3.7.10. At the time of the discovery, no fuel was being moved in the Auxiliary Building. The Shift Manager and Refueling Engineer were notified of the condition and concurred that fuel movement in the Auxiliary Building would not be allowed pending further investigation.
This occurrence is considered reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the plant's Technical Specifications.
B. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO
THE EVENT:
Spent Fuel Pool Charcoal Adsorber System
C. DATES AND APPROXIMATE TIMES OF MAJOR OCCURENCES:
- 9/27/06, charcoal sample withdrawn from Spent Fuel Pool Charcoal Adsorber System filter.
- 10/11/06, charcoal sample sent to NUCON International in Columbus, Ohio.
- 10/15/06, 1631, commenced movement of irradiated fuel in the Auxiliary Building. (Event date)
- 10/26/06, 1723, NUCON notified Ginna that the efficiency test of the charcoal sample had failed the test criteria of >85.5% efficiency. (Discovery date)
D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:
None
E. METHOD OF DISCOVERY:
Notification of vendor test results.
F. SAFETY SYSTEM RESPONSES:
No safety systems were actuated.
III.�CAUSE OF EVENT:
The cause of this event is that the laboratory results were received 11 days after irradiated fuel was moved in the Auxiliary building. Had the sample been sent out and tested earlier, this incident could have been avoided. Compared to past practices, a delay in obtaining a sample shortened the opportunity for advance warning of charcoal filter failure. Past practices had the samples taken at least one month prior to irradiated fuel moves. In this case, the sample was obtained about 18 days prior to irradiated fuel moves. A 12 day delay also occurred in shipping the sample to NUCON.
With regards to the charcoal sample test failure, an investigation determined that an incorrect filter face velocity had been used in the purchase order for the NUCON testing during 2002, 2003, and 2005. This incorrect test parameter resulted in a non-conservative result relative to actual face velocity conditions. The test results appeared satisfactory (e.g., above the Technical Specification value of 85.5%) when they were actually lower than reported. Since the previous test samples have been discarded, it is not possible to determine if the results from 2002, 2003, and 2005 were below Technical Specification values. There is also too much uncertainty to draw any inference about past operability. Because past testing used the wrong filter face velocity, charcoal degradation could not be previously identified, resulting in the inoperability.
Additional followup efficiency testing of other filter cells within the Spent Fuel Pool Charcoal Adsorber System resulted in test results ranging from 61.9% to 84.5% efficiency.
The cause of the incorrectly specified filter face velocity appears to be not following the procedural requirement for the calculation of the test velocity. Though required by the procedure, the request for testing form which is provided to the vendor does not specifically state to ensure the face velocity (ft/min) from the latest performance of the filter bank mass air flow check is entered. The same person submitted the purchase order for this test in 2000, 2002, 2003, and 2005. The filter face velocity was correct in 2000, but incorrect the next 3 times the purchase order was issued. This person is no longer employed at Ginna. The correct filter face velocity was submitted with the purchase order in 2006 by a different person. All other charcoal filtration systems have a fixed face velocity that is applied for testing, whereas this system has a calculation to determine the actual velocity. There is one other charcoal filtration system that uses a fixed test face velocity that is different from the standard face velocity of 40 ft/min. That is the Control Room Emergency Air treatment System (CREATS) which has a test face velocity of 61 ft/min. A review of the most recent CREATS test results validated that the correct test face velocity was used.
Discussion with the charcoal vendor (NUCON) identified that a 14 year life-time (the complete 33 filter bank was replaced in 1992 with new filters) for charcoal is about what is expected, although many variables contribute to the end of life, such as humidity, service time, temperature, etc. Although a charcoal poisoning event could not be ruled out, a comprehensive filter protection strategy has been in place throughout the time period that would prevent this type of event. No activities were identified that could have caused an event.
Based on the above, it is concluded that the most probable cause of the charcoal efficiency loss was end-of-life of the charcoal.
IV. ASSESSMENT OF THE SAFETY CONSEQUENCES OF THE EVENT:
This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B), which requires a report of, "Any operation or condition which was prohibited by the plant's Technical Specifications.
The operability of the Auxiliary Building Ventilation System (ABVS), and the Spent Fuel Pool Charcoal Adsorber System, ensures that in the event of a fuel handling accident in the auxiliary building that the offsite doses will remain well within the limits of 10 CFR 50.67. A dose sensitivity analysis was performed to assess the potential effect of the as-found condition of the Spent Fuel Pool Charcoal Adsorber System. The results of this analysis show that even with the degraded charcoal, that the fuel handling accident consequences are still well within the acceptance criteria (for the control room, approximately .2R TEDE compared to a limit of 5R TEDE). As such, the applicable regulatory acceptance criteria for design basis events would have been met and the Auxiliary Building Ventilation System remained capable of performing its intended safety function. Therefore, the reduced efficiency of the charcoal would not have adversely affected the health and safety of the public.
V. � CORRECTIVE ACTIONS:
A. � ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:
- Immediate actions included not allowing any fuel movements in the Auxiliary Building.
B. � ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:
- The charcoal filter media will be replaced.
- An evaluation will be conducted to determine if a change in the Technical Specification requirements should be processed
- The charcoal testing request form will be modified to prompt the individual to use the correct test filter face velocity as determined from the procedural requirements.
- An evaluation will be conducted to determine the appropriate schedule for obtaining the charcoal filter sample.
VI. � ADDITIONAL INFORMATION:
A. FAILED COMPONENTS:
No other structures, systems, or components failed as result of this event.
B. PREVIOUS LERs ON SIMILAR EVENTS:
A similar Ginna LER event historical search was conducted which resulted in no similar events.
C. THE ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) COMPONENT FUNCTION
IDENTIFIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO IN
THIS LER:
COMPONENT � IEEE 803 � IEEE 805 FUNCTION NUMBER � SYSTEM IDENTIFICATION Filter � FLT � VF
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05000305/LER-2006-010 | | | 05000456/LER-2006-001 | Unit 1 Reactor Coolant System Pressure Boundary Leakage Due To Inter-Granular Stress Corrosion Cracking of a Pressurizer Heater Sleeve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000454/LER-2006-001 | Technical Specification Required Action Completion Time Exceeded for Inoperable Containment Isolation Valves Due to Untimely Operability Determination | | 05000423/LER-2006-001 | Loss Of Safety Function Of The Control Room Emergency Ventilation System | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000369/LER-2006-001 | Ice Condenser and Floor Cooling System Containment Isolation Valve inoperable longer than allowed by Technical Specification 3.6.3. | | 05000353/LER-2006-001 | HPCI Ramp Generator Signal Converter Failure | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000352/LER-2006-001 | Loss Of One Offsite Circuit Due To Invalid Actuation Of Fire Suppression System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000336/LER-2006-001 | | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | 05000316/LER-2006-001 | Failure to Comply with Technical Specification 3.6.2, Containment Air Locks | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2006-001 | Plant Shutdown Required by Technical Specification Action 3.6.5.B.1 | | 05000293/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv), System Actuation | 05000289/LER-2006-001 | | | 05000287/LER-2006-001 | Actuation of Emergency Generator due to Spurious Transformer Lockout | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000251/LER-2006-001 | Turkey Point Unit 4 05000251 1 OF 6 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000247/LER-2006-001 | Manual Reactor Trip Due to Multiple Dropped Control Rods Caused by Loss of Control Rod Power Due to Personnel Error | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2006-001 | Incorrect Wiring in the Remote Shutdown Panel Results in a Fire Protection Program Violation | | 05000413/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000368/LER-2006-001 | Completion of a Plant Shutdown Required by Technical Specifications Due to Loss of Motive Power to Certain Containment Isolation Valves as a Result of a Phase to Ground Short Circuit in a Motor Control Cubicle | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000306/LER-2006-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000298/LER-2006-001 | Cooper Nuclear Station 05000298 1 of 4 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000286/LER-2006-001 | I | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000266/LER-2006-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000261/LER-2006-001 | Manual Reactor Trip Due to Failure of a Turbine Governor Valve Electro-Hydraulic Control Card | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000255/LER-2006-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000461/LER-2006-002 | Turbine Bypass Function Lost Due to Circuit Card Maintenance Frequency | | 05000458/LER-2006-002 | Loss of Safety Function of High Pressure Core Spray Due to Manual Deactivation | | 05000456/LER-2006-002 | Units 1 and 2 Entry into Limiting Condition for Operation 3.0.3 due to Main Control Room Ventilation Envelope Low Pressure | | 05000443/LER-2006-002 | Noncompliance with the Requirements of Technical Specification 6.8.1.2.a | | 05000387/LER-2006-002 | DMissed Technical Specification surveillance requirement | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000362/LER-2006-002 | Unit 3 Shutdown to Inspect Safety Injection Tank Spiral Wound Gaskets | | 05000336/LER-2006-002 | Manual Reactor Trip Due To Trip Of Both Feed Pumps Following A Loss Of Instrument Air | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000316/LER-2006-002 | | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2006-002 | Failure to Comply with Technical Specification Requirement 3.6.13, Divider Barrier Integrity | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2006-002 | | | 05000289/LER-2006-002 | | | 05000251/LER-2006-002 | Intermediate Range High Flux Trip Setpoint Exceeded Technical Specification Allowable Value | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000440/LER-2006-002 | Scaffold Built in the Containment Pool Swell Region | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000413/LER-2006-002 | Safe Shutdown Potentially Challenged by an External Flooding Event and Inadequate Design and Configuration Control | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000388/LER-2006-002 | Missed Technical Specification LCO 3.8.1 Entry for Unit 2 During Unit 1 ESS Bus Testing | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000348/LER-2006-002 | Main Steam Isolation Valve Failure to Close | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2006-002 | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000301/LER-2006-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000286/LER-2006-002 | 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249Entergy Tel (914) 734-6700 Fred Dacimo Site Vice President Administration September 13, 2006 Indian Point Unit No. 3 Docket No. 50-286 N L-06-084 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Subject:L Licensee Event Report # 2006-002-00, "Manual Reactor Trip as a Result of Arcing Under the Main Generator Between Scaffolding and Phase A&B of the Isophase Bus Housing" Dear Sir: The attached Licensee Event Report (LER) 2006-002-00 is the follow-up written report submitted in accordance with 10 CFR 50.73. This event is of the type defined in 10 CFR 50.73(a)(2)(iv)(A) for an event recorded in the Entergy corrective action process as Condition Report CR-IP3-2006-02255. There are no commitments contained in this letter. Should you or your staff have any questions regarding this matter, please contact Mr. Patric W. Conroy, Manager, Licensing, Indian Point Energy Center at (914) 734-6668. Fred R. Dacimo Site Vice President Indian Point Energy Center Docket No. 50-286 NL-06-084 Page 2 of 2 Attachment: LER-2006-002-00 CC: Mr. Samuel J. Collins Regional Administrator — Region I U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspector's Office Resident Inspector Indian Point Unit 3 Mr. Paul Eddy State of New York Public Service Commission INPO Record Center NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 06/30/2007
(6-2004)
. Estimated burden per response to comply with this mandatory collection request: 50 hours.DReported 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, Washington, DC 20555-0001, or by internetLICENSEE EVENT REPORT (LER) e-mail to infocollects@nrc.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 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. ■ 1. FACILITY NAME 2. DOCKET NUMBER I 3. PAGE
INDIAN POINT 3 05000-286 1 OF 6
4.TITLE: Manual Reactor Trip as a Result of Arcing Under the Main Generator Between
Scaffolding and Phase A&B of the Iso-phase Bus Housing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2006-002 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000269/LER-2006-002 | High Energy Line Breaks Outside Licensing Basis May Result in Loss of Safety Function | | 05000263/LER-2006-002 | | | 05000255/LER-2006-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000254/LER-2006-002 | Quad Cities Nuclear Power Station Unit 1 05000254 1 of 3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000483/LER-2006-003 | Unexpected Inoperability of the Emergency Exhaust System due to Inoperable Pressure Boundary | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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