Unit Status: At the time this historical condition was identified, Unit 1 and Unit 2 were in Mode 1 (Power Operation) at 100 percent power.
Event Description: On June 19, 2006, Ice Condenser Floor Cooling (NF) air operated outside containment isolation valves, 1NF-234 and 2NF-234, were determined to be inoperable on McGuire Unit 1 and Unit 2 for a period longer than allowed by Technical Specifications. Engineering identified a historical condition affecting these valves which could potentially allow them to open after their closure on a containment isolation signal. This event was not significant with respect to the health and safety of the public.
Event Cause: The cause for air operated containment isolation valves 1/2 NF-234 potentially not being able to remain closed after a containment isolation signal was attributed to inadequate actuator closing margin.
TThis inadequacy stemmed from non- conservative system pressure considerations for ITT Grinnell diaphragm valves during original design.
Corrective Actions: The valves were declared inoperable.TCompensatory actions were implemented to limit system pressure increase and to restore the valves to operable but degraded or non-conforming condition.TA safety grade relief valve was installed on each Unit to limit system pressure increase and to return the components to fully operable status. |
LER-2006-001, Ice Condenser and Floor Cooling System Containment Isolation Valve inoperable longer than allowed by Technical Specification 3.6.3.Docket Number |
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3692006001R00 - NRC Website |
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BACKGROUND
Applicable Energy Industry Identification (EIIS) system and component codes are enclosed within brackets. McGuire unique system and component identifiers are contained within parentheses.
The Ice Condenser Refrigeration system (NF) [BC] serves as a central heat sink for sensible heat picked up in the ice condenser. During normal plant operation, a circulating loop of corrosion inhibited glycol/water solution carries the heat from the ice condenser air handling units, the floor cooling system and the ice machines (when operating) to the evaporator and heat is removed from the chiller unit by cooling water flowing through the condenser. The chiller units operate individually to maintain containment return temperature of glycol/water solution at or below approximately 1 degree Fahrenheit. This system is not safety related. During a design basis accident, glycol/water flow is terminated by containment isolation valves which are closed automatically. As the glycol/water solution heats up to ambient temperature and expands, the resultant pressure increase is limited on the containment side by an expansion tank which is vented into the containment, and on the Auxiliary building side by a relief valve with a relief setting of 180 psig. The containment isolation function of the NF system is safety related.
The Containment Isolation System provides the means of isolating fluid systems that pass through Containment penetrations so as to confine any radioactivity that may be released following a design basis event. The Containment Isolation System is required to function following a design basis event to isolate non-essential fluid systems penetrating the Containment.
Glycol lines of the NF system penetrating the containment are provided with fail closed, air operated, containment isolation valves, which close automatically upon receipt of a containment isolation signal.
For the glycol return line penetration, M-372, 1/2 NF-233 provide the inside containment isolation function and 1/2 NF-234 provide the outside containment isolation function. For the glycol inlet line penetration, M 373, a failed closed air operated valve outside containment, 1/2 NF-228, and a soft seated spring loaded check valve, 1/2 NF-229, are provided for containment isolation function.
The air operated NF valves are 4 inch diaphragm valves. Due to the large surface area of the internal diaphragm, system pressure creates a relatively The highest force opposing the actuator spring occurs when the line pressure upstream and downstream of the valve is at maximum.
large force opposing actuator thrust output.
The valve control logic is such that the closed direction limit switch is used to provide a "seal-in" function for the valve solenoid to keep the valve open once the open push button is pressed. If the increased system pressure opened the valve to the point where the limit switch was reset, then the associated solenoid valve would be energized and the valve would fully open. A containment isolation signal being present would prevent the solenoid valve from energizing, but if the signal was removed (reset), the solenoid would be energized and the containment isolation function of this valve would not have been performed.
McGuire Technical Specification (TS) 3.6.3 - Containment Isolation Valves:
TS 3.6.3 specifies that each containment isolation valve (CIV) [ISV] shall be operable in Modes 1, 2, 3, and 4. Condition A requires, in part, that in the event one CIV in one or more penetration flow paths is inoperable, the affected penetration flow path must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Condition F states that if the required action and associated completion time is not met, the respective Unit must 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 in Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
EVENT DESCRIPTION
At the time this historical condition was identified, McGuire Unit 1 and Unit 2 were in Mode 1 at 100% power. No systems, structures, or components were out of service at the time of this event which contributed to this event.
In May 2006, the NF system calculation was issued with new system pressure design conditions in accordance with the Air Operated Valve (AOV) improvement plan.
On June 15, 2006, the plant corrective action process (PIP) was entered to document that the newly formulated system design conditions could affect closing margin on the NF containment isolation valves (1/2 NF-228, 1/2 NF 233, 1/2 NF-234).
On June 16, 2006, 1/2 NF-234 were conservatively declared inoperable due to concerns that 1/2 NF-234 would not remain closed following the receipt of the containment isolation signal. Compensatory actions were implemented to limit the pressure increase and to restore the valves to operable but degraded or non-conforming status.
On June 19, 2006, the operability determination process confirmed that for 1/2 NF-234, the internal force due to system pressure was large enough to exceed the actuator's capability to hold the valves closed such that the valves may be off its closed seat. Considering the valve's control logic, the valves may have fully opened and not be capable of re-closing when the containment isolation signal was reset. This process identified that 1/2 NF-228, and 1/2 NF-233 would function as designed.
On July 10, 2006, 1/2 NF-234 were declared fully operable when a safety grade relief valve with a lift setting of 70 psig was installed on each Unit to limit pressure increase outside containment.
Since valves 1/2 NF-234 could potentially reposition after a containment isolation signal, they were not considered fully operable per TS 3.6.3.
Consequently, these valves were inoperable for a period longer than allowed by TS. This condition represented an operation prohibited by Technical Specifications and is reportable per the requirements of 10 CFR 50.73 (a)(2)(i)(B).
CAUSAL FACTORS
The cause for air operated containment isolation valves 1/2 NF-234 not being able to remain closed after a containment isolation signal was attributed to inadequate actuator closing margin. This inadequacy stemmed from non- conservative system pressure considerations for ITT Grinnell diaphragm valves during original design.
CORRECTIVE ACTIONS
IMMEDIATE
- Valves 1/2 NF-234 were declared inoperable.
- Compensatory actions were implemented on both units to restore the valves to an operable but degraded or non-conforming condition.
SUBSEQUENT
- Installed a safety grade relief valve to limit pressure increase outside containment and to resolve the degraded or non-conforming condition.
- Engineering reviewed information contained in the valve calculations to ensure proper NF system conditions have been applied.
Planned
- Evaluate design enhancements for the "seal-in" circuitry on failed closed ITT Grinnell diaphragm containment isolation valves to address design vulnerabilities related to this function.
- Review information contained in other system valve calculations which are susceptible to the thermal pressurization mechanism that utilize diaphragm valves with AOVs.
- Review the sizing of active motor operated ITT Grinnell diaphragm containment isolation valves based on expected system conditions.
SAFETY ANALYSIS
Failure of 1/2 NF-234 would have not prevented isolation of mechanical penetration M-372, when the containment isolation signal is reset, following its initial closure. The inside containment isolation valves 1/2 NF-233 would have remained closed during this event and isolated this penetration flow path.
If 1/2 NF-233 failed to close for any reason, the pressure between the two containment isolation valves would not increase to the point where 1/2NF-234 would be lifted off the closed seat. Thus, following containment isolation reset valves 1/2 NF-234 would remain closed and provide the mechanical penetration M-372 isolation.
A review of this event determined that there is no impact on either the estimated core damage frequency (CDF) or large early release frequency (LERF). Therefore, the event described in this LER was not significant with respect to the health and safety of the public.
ADDITIONAL INFORMATION
A review of the McGuire corrective action database did not identify any other events within the past three years having similar circumstances, cause, and corrective actions. Therefore, the event described in this LER is not considered a recurring event.
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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 - 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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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