04-12-2005 | On 02/14/2005, at 2155 PST, with Unit 2 at 96 percent power, plant operators manually initiated a plant shutdown to repair 2HV6500, a Component Cooling Water ( CCW) valve.
In accordance with 10 CFR 50.72(b)(2)(i), SCE reported initiation of the shutdown to the NRC on 02/14/2005 (Log No. 41410) at 2213 PST. The plant reached Mode 5 at 1804 PST on 02/15/2005. SCE is submitting this report in accordance with 10 CFR 50.73(a)(2)(i)(A).� I 2HV6500 is the Train "B" CCW outlet isolation valve for the Shutdown Cooling (SDC) heat exchanger. The Containment Spray (CS) system depends on SDC heat exchanger availability for system operability. In response to an abnormal reduced flow condition in 2HV6500, plant operators declared the valve inoperable on 02/10/2005 at 2315 PST and entered the 7-day allowed outage time to restore the CS system. SCE conservatively decided to shutdown the plant to repair the valve.
Upon disassembling 2HV6500, the two taper pins securing the valve disc to the stem were missing. New pins were installed and staked to the disc and the valve was returned to service. SCE will screen similar valves to determine which valves require follow-up inspection. Safety significance was minimal. The CS system has two independent trains. During the time Train "B" CS was declared inoperable, Train "A" remained operable and available to fulfill its safety function. |
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LER-2005-002, Missing Taper Pins on CCW Valve Cause Technical Specification Required ShutdownDocket Number |
Event date: |
02-15-2005 |
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Report date: |
04-12-2005 |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
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3612005002R00 - NRC Website |
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1. FACIUTY NAME 2. DOCKET NUMBER 6. LER NUMBER PAGE (3) Event Date: February 15, 2005 Reactor Vendor: Combustion Engineering Mode: Mode 3, Shutdown Power: 0 percent
Description of Event
Valve 2HV6500 [V] is the Train "B" Component Cooling Water (CCW)[CC] outlet isolation valve for the Shutdown Cooling (SDC)[BP] heat exchanger [HX]. The Containment Spray (CS)[BE] system depends on SDC heat exchanger availability for system operability.
San Onofre Unit 2 Technical Specification (TS) 3.6.6.1 for "Containment Spray and Cooling Systems" requires two trains of CS and two containment cooling trains to be operable in Modes 1 through 3. With one train of CS inoperable, action "A" requires SCE to restore the inoperable train within 7 days. If not completed within that time, action "B" requires SCE to place the plant in Mode 3 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Mode 4 in 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.
On February 10, 2005 at 2315 PST, plant operators declared valve 2HV6500 inoperable in response to an abnormal reduced flow condition. Operators also declared Train "B" of CS inoperable and entered the 7-day allowed outage time to restore the system.
SCE was uncertain whether 2HV6500 could be repaired within the allowed outage time of TS 3.6.6.1 (7 days) and conservatively decided to shutdown the plant. Therefore to repair 2HV6500, on February 14, 2005, at 2155 PST plant operators (utility, licensed) manually initiated a plant shutdown in accordance with procedures. Plant equipment performed as expected. In accordance with 10 CFR 50.72(b)(2)(i), SCE reported initiation of the shutdown to the NRC Operations Center (Log No. 41410) at 2213 PST on February 14, 2005.
The Unit reached Mode 3 at 0241 PST on February 15, 2005 and Mode 5 at 1804 PST that same day. In accordance with 10 CFR 50.73(a)(2)(i)(A), SCE is submitting this Licensee Event Report for completion of the TS required plant shutdown.
Cause of Event
SCE disassembled 2HV6500 and determined the abnormal flow was caused by the valve disc not being fully connected to the valve stem. 2HV6500 is an 18-inch Fisher Controls (model no. 9211) butterfly valve that uses two taper pins to secure the valve disc to the stem. By design, the pins are impact-driven into holes drilled in the disc and stem, and are held in place solely by the resulting interference fit. SCE concluded the interference-fit taper pins had come free and no longer attached the valve disc to the stem and this condition prevented the valve from fully opening.
1. FACLITY RAW 2. DOCKET NUMBER 6.LER NUMBER PAGE (3) SCE was not able to conclusively determine why the taper pins lost their interference fit.
(see "Generic Considerations" discussion below).
Corrective Actions
SCE reattached and secured the 2HV6500 valve disc to its stem with new taper pins and staked the pins to the disc. SCE leak tested the valve and performed post-maintenance Air Operated Valve diagnostic testing prior to return to service.
It should be noted that SCE is also implementing corrective actions for taper pins on Fisher Controls butterfly valves in critical plant applications. (See Additional Information section below).
Safety Significance
The SONGS Unit 2 containment spray system has two independent trains. During the time Train "B" containment spray was declared inoperable, Train "A" remained operable and available to fulfill its safety function.
An assessment of the incremental core damage probability (ICDP) and the incremental large early release probability (ILERP) for the 2HV6500 failure event determined that the Unit 2 ICDP and ILERP were 2.1E-7 and 5.5E-9, respectively. Therefore the safety significance of this event was minimal. The assessment was based on the reported actual system alignments, component unavailability (including 2HV6500) and operating conditions that existed from the time of discovery on February 10, 2005 through the plant shutdown on February 15, 2005.
Additional Information
Previous events:
In the past three years, SCE submitted one other LER involving initiation of a TS required plant shutdown. Unit 3 LER 2003-001, dated February 15, 2004, reported the initiation of a TS 3.0.3 shutdown when two trains of safety related equipment became inoperable. That event was caused by a failure of a load center feeder breaker at the same time the redundant safety related equipment was out of service for planned maintenance. Corrective actions for that event focused on breaker-related issues and could not have prevented the failure of valve 2HV6500 reported above.
Ongoing Taper Pin Related Corrective Actions:
In 1993, SCE discovered two 28-inch Fisher Controls butterfly valves (model no. 9200) in Unit 2, each with a missing a taper pin. These valves were associated with CCW Pump 2P025. At that time, SCE contacted Fisher Controls regarding the missing taper pins and Fisher Controls concluded these were isolated occurrences.
1. FACUTY NAME 2. DOCKET NUMBER 6. LER NUMBER PAGE (3) In 1998, SCE observed leakage at two other 28-inch Fisher Controls butterfly valves (also model no. 9200) in Unit 3. These valves were subsequently scheduled for inspection during the Unit 3 Cycle 13 refueling outage (September 27, 2004 - December 28, 2004). Just before the refueling outage, a third butterfly valve developed a leak. All three valves were associated with the CCW Pump 3P025 suction or discharge. Inspections found that one taper pin was missing from each valve disc stem assembly. (There are five taper pins in each 28-inch valve and not all pins are required for valve operability.) As a result of the findings, SCE expanded its inspection scope during the Unit 3 2004 refueling outage. At the time, SCE believed that only Fisher Controls butterfly valves associated with the suction and discharge of CCW Pump 2(3)P025 were susceptible to loss of taper pins. The inspection scope screened all butterfly valves in critical safety related applications and inspected those valves where leakage through a missing taper pin could not be tolerated. This resulted in the inspection of sixteen other Fisher Controls butterfly valves of which a few had improperly seated taper pins. SCE staked the taper pins in each inspected valve.
After the failure of 2HV6500 (the CCW discharge valve for the Train "B" SDC heat exchanger), SCE revised its screening criteria to include all butterfly valves in critical safety related applications where loss of valve function or leakage through a missing taper pin could not be tolerated. Based on this screen, SCE will determine which valves require inspection. The inspections are planned for upcoming Unit 2 and 3 refueling outages. SCE intends to stake all taper pins in the valves inspected during the outages.
Generic Considerations:
Since 1993, SCE has discovered five 28-inch butterfly valves that had a single missing taper pin. Fisher Controls does not specify any required inspections for the taper pins and SCE had not disassembled the valves prior to discovery of the missing taper pins.
During discussions with SCE, in both 1993 and 2004, Fisher Controls indicated that similar taper pin failures were not being reported from other licensees.
With the recent 2HV6500 (18-inch model 9211) butterfly valve issue, missing taper pins do not appear to be isolated to the specific hydraulic conditions surrounding CCW Pump 2(3)P025 and may indicate broader manufacturing issues.
Due to the nature and extent of the taper pin failures, other licensees using Fisher Controls butterfly valves with interference fit taper pins may experience similar failures at their facilities.
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Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000247/LER-2005-002 | DTechnical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for One Inoperable Train of ECCS Caused by Gas Intrusion from a Leaking Check Valve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000306/LER-2005-002 | | 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 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000265/LER-2005-002 | Main Steam Relief Valve Actuator Degradation Due to Failure to Correct Vibration Levels Exceeding Equipment Design Capacities | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000286/LER-2005-002 | • Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249Entergy Buchanan. NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration July 5, 2005 Indian Point Unit No. 3 Docket Nos. 50-286 N L-05-078 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Subject:L Licensee Event Report # 2005-002-00, "Automatic Reactor Trip Due to 32 Steam Generator Steam Flow/Feedwater Flow Mismatch Caused by Low Feedwater Flow Due to Inadvertent Condensate Polisher Post Filter Bypass Valve Closure." Dear Sir: The attached Licensee Event Report (LER) 2005-002-00 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-IP3-2005-02478. 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. Sincerely, 4F-/t R. Dacimo Vice President Indian Point Energy Center Docket No. 50-286 NL-05-078 Page 2 of 2 Attachment: LER-2005-002-00 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 3660 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.RReported lessons teamed 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 29555-0001, or by InternetLICENSEE EVENT REPORT (LER) e-mail to Infocoilectsenrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-l0202, (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. FACIUTY NAME 2. DOCKET NUMBER 3. PAGE INDIAN POINT 3 05000-286 10OF06 4. TITLE Automatic Reactor Trip Due to 32 Steam Generator Steam Flow/Feedwater Flow Mismatch Caused by Low Feedwater Flow Due to Inadvertent Condensate Polisher Post Filter Bypass Valve Closure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000287/LER-2005-002 | Unit 3 trip with ES actuation due to CRD Modification Deficiencies | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000336/LER-2005-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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