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Category:Letter
MONTHYEARML24304B0512024-10-30030 October 2024 Cycle 26 Core Operating Limits Report IR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24290A1162024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance NOC-AE-240040, Nuclear Liability Certificates of Insurance2024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 ML24022A2252024-02-20020 February 2024 Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation ML24050A0082024-02-19019 February 2024 Evidence of Financial Protection ML24045A0922024-02-16016 February 2024 Response to STP FOF Move Letter (2024) 2024-09-30
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-004, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-02-0505 February 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water 05000499/LER-2023-002, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus2024-01-30030 January 2024 Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus 05000499/LER-2023-001, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-01-15015 January 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-01-0909 January 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-001-01, Supplement to Pressurizer Power Operated Valve Failed to Open2023-07-26026 July 2023 Supplement to Pressurizer Power Operated Valve Failed to Open 05000498/LER-2023-001, Pressurizer Power Operated Relief Valve Failed to Open2023-06-12012 June 2023 Pressurizer Power Operated Relief Valve Failed to Open 05000499/LER-2021-002-01, Supplement to Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System2022-07-0505 July 2022 Supplement to Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System 05000499/LER-2022-001, From South Texas Project Unit 2, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus2022-03-0303 March 2022 From South Texas Project Unit 2, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus 05000499/LER-2021-002, Re Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System2021-12-21021 December 2021 Re Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System 05000499/LER-2021-001, Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve2021-09-0909 September 2021 Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve 05000498/LER-2017-0022018-01-22022 January 2018 Unit 1 Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil, LER 17-002-00 for South Texas Project, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil 05000498/LER-2017-0012017-05-11011 May 2017 Unit 1 failure of a timing relay during a Technical Specification surveillance, LER 17-001-00 for South Texas, Unit 1, Regarding Failure of a Timing Relay During a Technical Specification Surveillance 05000498/LER-2016-0022016-06-29029 June 2016 Unit 1 Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip due to Generator Lockout, LER 16-002-00 for South Texas Project, Unit 1, Regarding Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip Due to Generator Lockout 05000498/LER-2016-0012016-03-22022 March 2016 Unit 1 Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed, LER 16-001-00 for South Texas Project, Unit 1, Regarding Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed NOC-AE-05001865, LER 05-01-00 South Texas Project Unit 2 Regarding Shutdown of STP Unit 2 Due to Reactor Coolant System Pressure Boundary Leak2005-04-0505 April 2005 LER 05-01-00 South Texas Project Unit 2 Regarding Shutdown of STP Unit 2 Due to Reactor Coolant System Pressure Boundary Leak NOC-AE-04001681, LER 01-03-007 for South Texas, Unit 1 Regarding Failure of Main Steam Power Operated Relief Valves 1B2004-02-18018 February 2004 LER 01-03-007 for South Texas, Unit 1 Regarding Failure of Main Steam Power Operated Relief Valves 1B NOC-AE-00000840, 1,Unauthorized Entry Into Protected Area,Safeguards Event Report2000-05-0404 May 2000 1,Unauthorized Entry Into Protected Area,Safeguards Event Report 2024-09-19
[Table view] |
LER-2021-001, Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve |
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Nuclear Operating Company
South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, Texas 77483
September 9, 2021 NOC-AE-21003833 10 CFR 50.73 STI:35208185
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
South Texas Project Unit 2 Docket No. STN 50-499 Licensee Event Report 2021-001-00 Condition Prohibited by Technical Specifications Due to InoperabteC^^^ Valve
Pursuant to 10 CFR 50.73(a)(2)(i)(B), STP Nuclear Operating Company submits South Texas Project (STP) Unit 2 Licensee Event Report 2021-001-00 for a condition prohibited by Technical Specifications due to an inoperable containment isolation valve. This event is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B) because the Technical Specification 3.6.3 required action statement for an inoperable containment isolation valve was not met.
The event did not have an adverse effect on the health and safety of the public.
There are no commitments in this letter.
If you should have any questions on this submittal, please contact All Albaaj at (361) 972-8949 or me at (361) 972-4778. k^UW^-"
Kimberly A. Harshaw Executive Vice President and Acting Chief Nuclear Officer
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Attachment: STP Unit 2 LER 2021-001-00, Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve
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Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511 NOC-AE-21003833 Attachment
Attachment
STP Unit 2 LER 2021-001-00, Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve
Abstract
On July 1, 2021, at 2344 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.91892e-4 months <br />, the STP Nuclear Operating Company discovered that Steam Generator 2D outside reactor containment isolation valve R/-4150 was indicating valve closure but only reduced the flow rate by about 8.33%. On July 2, 2021, at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />, the valve was declared inoperable due to inadequate isolation. Site engineering determined on July 12, 2021, that FV-4150 was inoperable since March 29, 2021, due to preventative maintenance performed on that date. On July 3, 2021, FV-4150 was determined to be operable following a valve stem adjustment and a satisfactory performance of the surveillance test.
The causes of the event were associated with inadequate written guidance. This event is reportable because the Technical Specification 3.6.3 required action statement for an inoperable containment isolation valve was not met. Specifically, the containment isolation valve was inoperable from March 29, 2021, to July 3, 2021, for a total of 96 days. The allowed outage time is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or apply the requirements of the configuration risk management program. Planned corrective actions include revising the work instructions and the post-maintenance testing guidance.
I. Description of Reportable Event
A. Reportable event classification
This event is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B) because the Technical Specification 3.6.3 required action statement for an inoperable containment isolation valve was not met.
B. Plant operating conditions prior to event
Prior to the event, Unit 2 was at 100% power in Mode 1.
C. Status of structures, systems, and components that were INOPERABLE at the start of the event and that contributed to the event
No other structures, systems, or components were inoperable at the start of this event that contributed to this event.
D. Background information
The steam generator blowdown system provides the means to continuously blowdown the steam generator to maintain the prescribed water chemistry in the steam generators. The system also removes dissolved solids and corrosion products from the blowdown stream to make it suitable for reuse in the condenser hotwell.
The steam generator blowdown system is a closed system. Steam Generator 2D outside reactor containment isolation valve R/-4150 meets the requirements in General Design Criteria 57 for Closed Systems Isolation Valves. There was no open pathway between the reactor containment building and the outside.
E. Narrative summary of the event
Note: all times are Central Daylight Time
On July 1,2021, at 2344 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.91892e-4 months <br />, a condition report was written documenting that during the performance of the steam generator blowdown system valve operability test, Steam Generator 2D outside reactor containment isolation valve R/-41 50 local valve indication showed closed. However, the flow across the valve only reduced from about 36 klb/hrto about 33 klb/hr. On July 2, 2021, at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />, R/-41 50 was declared inoperable due to inadequate isolation.
Corrective maintenance was performed on the valve on July 2, 2021. The as-found condition was described as "craft identified valve was not making contact with the valve seat." The valve stem was screwed out three turns from the marriage block, adjusting the valve stroke to bring the valve plug to the seat. This indicated the valve stroke was slightly short, not allowing the plug to contact the valve seat. R/-4150 is quick-opening, thus only a slight distance between the seat and the plug is necessary for the valve to allow a large percentage of flow through while closed.
On July 3, 2021, at 0501 hours0.0058 days <br />0.139 hours <br />8.28373e-4 weeks <br />1.906305e-4 months <br />, R/-4150 passed the steam generator blowdown system valve operability test and was declared operable. Site engineering determined on July 12, 2021, that the valve stroke length inaccuracy was the result of an actuator overhaul preventative maintenance activity that was completed on March 29, 2021, duhng the most recent refueling outage (2RE21). The scope of the preventative maintenance was to disassemble the actuator, replace soft parts and worn or damaged parts, measure the free length of the actuator spring, replace air filter, and reassemble. Under this preventative maintenance, the actuator stem is removed, and the stroke of the actuator is adjusted.
F. Method of discovery
This event was self-revealed when R/-4150 did not pass the quarterly sun/eillance test due to inadequate isolation.
II. Component failures
A. Failure Mode, mechanism, and effects of failed component
The failed component of this event was the steam generator 2D blowdown valve FV-4150. The valve plug was not contacting the valve seat creating a slightly short valve stroke. There were no effects on safety systems and functions due to the failed component because the steam generator blowdown system is a closed system. The steam generator blowdown valve is an outside containment isolation valve and meets the requirements of General Design Criteria 57 for Closed Systems Isolation Valves. There were no other components affected by the failed component.
B. Cause of component or system failure or personnel error
The direct cause of this event was the valve stem was seated in the marriage block short, shortening the valve stroke and not allowing the plug to contact the valve seat.
C. Systems or secondary functions that were affected by failure of components with multiple functions
There are no secondary systems or functions for this component.
D. Failed component information
Steam generator blowdown system outside reactor containment isolation valve;
4-inch ASME Section III, Class 2, quick-opening type globe valve
III. Analysis of the event
A. Safety system responses that occurred
No safety system responses occurred due to this event.
B. Duration of safety system inoperability
Steam Generator 2D blowdown outside reactor containment isolation valve R/-41 50 was inoperable from March 29, 2021, to July 3, 2021, for a total of 96 days.
C. Safety consequences and implications
Valve FV-4150 is connected to the secondary side of Steam Generator 2D and not directly connected to containment atmosphere. Secondary water exiting through the blowdown line will enter the condenser hotwell and return to Steam Generator 2D as main feedwater. The steam generator blowdown system is a closed system. The steam generator blowdown valve is an outside containment isolation valve and meets the requirements of General Design Criteria 57 for Closed Systems Isolation Valves. There is no open pathway in the physical integrity of reactor containment due to an inoperable blowdown valve. This event did not result in any offsite release of radioactivity or increase of offsite dose rates, and there were no personnel injuries or damage to any safety-related equipment associated with this event. Therefore, there was no adverse effect on the health and safety of the public.
IV. Cause of the event
The causes for this event were determined to be:
- 1. Vendor Technical Document work instructions do not work as written when leaving the actuator installed during actuator disassembly.
- 2. Post-Maintenance Testing did not include guidance to ensure valve plug was fully seated.
- 3. The valve remote position indicator verification test procedure assumes the local valve position indication reflects the actual (internal) valve position.
V. Corrective actions
Planned corrective actions are as follows:
- 1. Revise Vendor Technical Document for containment isolation valve FV-4150 to ensure the work instructions for "Reassembling the Actuator" work as written if the actuator is disassembled while on the valve in accordance with the work instructions for "Disassembling the Actuator."
- 2. Revise Maintenance Work Instructions to include the following post-maintenance testing guidance:
Perform Valve Diagnostic Testing to ensure full open and close stroke of valve.
Verify the valve plug is fully seated in the closed position.
Verify correct local and remote indication of valve position in the open and closed position.
No corrective actions were determined to be necessary for Cause 3. The remote position indication and the local valve position indicator are verified accurate during post-maintenance testing under maintenance guidance via valve diagnostic testing (Cause 2). This will establish reasonable assurance of the validity of the subsequent performances of the valve remote position indicator verification test and the steam generator blowdown system valve operability test.
VI. Previous similar events
No previous similar events were identified.