Similar Documents at Salem |
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Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 ML23034A1532023-02-0909 February 2023 Operator Licensing Examination Approval ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 2024-02-05
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000272/LER-2017-0012018-01-0808 January 2018 Containment Integrity Inoperable for Longer than Allowed by Technical Specifications, LER 17-001-00 for Salem Generating Station, Unit 1 Regarding Containment Integrity Inoperable for Longer than Allowed by Technical Specifications 05000311/LER-2016-0022017-09-0707 September 2017 Automatic Reactor Trip due to Main Turbine Trip, LER 16-002-01 for Salem, Unit 2, Regarding Automatic Reactor Trip Due to Main Turbine Trip 05000311/LER-2015-0022017-09-0707 September 2017 P.O. Box 236, Hancocks Bridge, NJ 08038-0236 PSEG Nadea, II,C OCT 0 2 2015 LR-N15-0205 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LER 311/2015-002-00 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 SUBJECT: Licensee Event Report 311/2015-002-00 In accordance with the requirements of 10 CFR 50.73(a)(2)(iv), PSEG Nuclear LLC is submitting the enclosed Licensee Event Report (LER) Number 2015-002-00, "Reactor Trip Due to Loss of 4kV Non-Vital Group Bus." There are no regulatory commitments contained in this letter. If you have any questions or require additional information, please contact Mr. David Lafleur of Salem Regulatory Assurance at 856-339-1754. Sincerely, John F. Perry Site Vice President — alem Attachment OCT 0 2 2015 10 CFR 50.73 Page 2 LR-N15-0205 CC Mr. D. Dorman, Administrator— Region 1, NRC Mr. T. Wengert, Licensing Project Manager (acting) — Salem, NRC Mr. P. Finney, USNRC Senior Resident Inspector, Salem (X24) Mr. P. Mulligan, Manager IV, NJBNE Mr. R. Braun, President and Chief Nuclear Officer — Nuclear Mr. T. Cachaza, Salem Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. D. Lafleur, Salem Regulatory Assurance NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 01-2014) t, , .1 • '., LICENSEE EVENT REPORT (LER) 'S ree Page 2 or required number of digits/characters for each block) APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0113112017 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 comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mall to Infocollects.Resource@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 currentlyvaild 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 Salem Generating Station - Unit 2 2. DOCKET NUMBER 05000311 3. PAGE 1 OF 4 4. TrrLE Reactor Trip Due to Loss of 4 kV Non-Vital Group Bus, LER 15-002-01 for Salem, Unit 2, Regarding Reactor Trip Due to Loss of 4 kV Non-Vital Group Bus 05000311/LER-2017-0012017-06-13013 June 2017 Emergency Diesel Generator Start Due to a Loss of Power to the 2C 4160 Volt Vital Bus, LER 17-001-00 for Salem, Unit 2, Regarding Emergency Diesel Generator Start Due to a Loss of Power to the 2C 4160 Volt Vital Bus 05000272/LER-2015-0022016-11-16016 November 2016 Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable, LER 15-002-002 for Salem, Unit 1, Regarding Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable 05000311/LER-2016-0062016-10-31031 October 2016 Automatic Reactor Trip Due to Trip of the 21 Reactor Coolant Pump, LER 16-006-00 for Salem, Unit 2, Regarding Automatic Reactor Trip Due to Trip of the 21 Reactor Coolant Pump 05000311/LER-2016-0052016-08-29029 August 2016 Automatic Reactor Trip due to Main Generator Protection Trip, LER 16-005-00 for Salem Generating Station, Unit 2 Regarding Automatic Reactor Trip due to Main Generator Protection Trip 05000272/LER-2016-0012016-07-0505 July 2016 Unanalyzed Condition due to Degraded Reactor Baffle to Former Bolts, LER 16-001-00 for Salem, Unit 1, Regarding Unanalyzed Condition due to Degraded Reactor Baffle to Former Bolts 05000311/LER-2016-0032016-04-14014 April 2016 Automatic Reactor Trip due to Main Generator Protection Trip, LER 16-003-00 for Salem, Unit 2, Regarding Automatic Reactor Trip due to Main Generator Protection Trip 05000311/LER-2016-0012016-03-21021 March 2016 AFW Loop Response Time Exceeded Technical Specifications, LER 16-001-00 for Salem, Unit 2, Regarding AFW Loop Response Time Exceeded Technical Specifications 05000272/LER-2015-0072016-01-29029 January 2016 Inoperable Control Room Emergency Air Conditioning System Due to Failed Charcoal Filter Surveillance Test, LER 15-007-01 for Salem, Unit 1, Regarding Inoperable Control Room Emergency Air Conditioning System Due to Failed Charcoal Filter Surveillance Test 05000311/LER-2015-0032016-01-22022 January 2016 Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure, LER 15-003-00 for Salem, Unit 2, Regarding Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure LR-N14-0128, Special Report 311/14-04-00, Pursuant to the Requirements of Technical Specification (TS) 3.4.10.3, Action D, for Overpressure Protection System Used to Mitigate an RCS Pressure Transient2014-05-13013 May 2014 Special Report 311/14-04-00, Pursuant to the Requirements of Technical Specification (TS) 3.4.10.3, Action D, for Overpressure Protection System Used to Mitigate an RCS Pressure Transient ML1015505772010-04-0808 April 2010 Event Notification for Salem on Storm Drain System Tested Positive for Tritium ML1034404492010-04-0505 April 2010 Document: Apparent Cause Evaluation Template Document: from Robert Montgomery LR-N05-0419, LER 05-04-00 for Salem Generating Station, Unit 2 Regarding Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves2005-08-15015 August 2005 LER 05-04-00 for Salem Generating Station, Unit 2 Regarding Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves ML0435704542004-12-13013 December 2004 Special Report 311/04-010 for Salem Unit 2 Regarding the 2R45 Detector Being Inoperable on 12/01/2004 ML19030A6261980-03-0303 March 1980 Licensee Event Report Inoperability of Air Particulate Detector Pump ML19031B0801978-09-18018 September 1978 Submit Licensee Event Report for Reportable Occurrence 78-56/03L ML19031B0381978-08-24024 August 1978 LER 1978-042-03 for Salem Unit 1 Excessive Trip Setpoint During Functional Test on No. 13 S/G Steam Flow Channel 1 ML19031B5091978-08-24024 August 1978 LER 1978 for Reportable Occurrence 78-45/03L on 100 Ft. Elevation Personnel Airlock Inoperable ML19031B5101978-08-24024 August 1978 LER 1978 for Reportable Occurrence 78-43/03L on Quadrant Power Tilt Ratio Greater than 1.02 ML19031B0361978-08-24024 August 1978 LER 1978-044-03 for Salem Unit 1 Inoperability of No. 11 S/G Feedwater Flow Channel 2 ML19031A8951978-08-14014 August 1978 LER 1978-041-03 for Salem Unit 1 Excessive Quadrant Power Tilt Ratio During Power Escalation ML19031B0391978-08-0303 August 1978 LER 1978-040-03 for Salem Unit 1 Inoperability of Makeup Valve from Demineralized Water Plant ML19031B5121978-08-0202 August 1978 Licensee Event Report 1978 for Reportable Occurrence 78-39/03L Re No. 13 Containment Fan Foil Unit Inoperable ML19031B5111978-08-0202 August 1978 Licensee Event Report 1978 for Reportable Occurrence 78-38/03L Re No. 11 Steam Generator Flow Channel II Inoperable ML19031B5131978-07-20020 July 1978 Licensee Event Report 1978 for Reportable Occurrence 78-36/03L Re Vital Bus Under Voltage Relay Setting Outside Technical Specification Limit ML19031C0301978-07-20020 July 1978 07/20/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids ML19031B1651978-07-20020 July 1978 LER 1978-035-03 for Salem Unit 1 Loss of Power to No. 2 Station Power Transformer ML19031B0401978-07-12012 July 1978 LER 1978-033-03 for Salem Unit 1 No. 11 Steam Generator Steam Flow Channel II ML19031B1671978-07-12012 July 1978 LER 1978-026-03 for Salem Unit 1 Failure of Motor Operated Valve ML19031C0311978-07-12012 July 1978 07/12/1978 Letter Reportable Occurrence on Missed Surveillance of Monthly Functional Test of Steam Generator Blowdown Radiation Monitoring Channels ML19031B5151978-07-10010 July 1978 Licensee Event Report 1978 for Reportable Occurrence 78-30/03L Re Control Bank and Shutdown Rod Misalignment ML19031B0411978-06-30030 June 1978 LER 1978-027-03 for Salem Unit 1 Malfunctioning Exterior Door of Containment Entry Air Lock ML19031B5171978-06-30030 June 1978 No. 1 - Licensee Event Report 1978 for Reportable Occurrence 78-28/03L Re Inoperable 100 Ft. Elevation Air Lock Interior Door ML19031C0321978-06-28028 June 1978 06/28/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids Analysis ML19031A8191978-06-21021 June 1978 LER 1978-029-01 for Salem Unit 1 Inoperability of Two Power Range Channels During Training Startups ML19031B5191978-05-15015 May 1978 LER 1978-025-03 for Salem Generating Station Unit 1 Re Missed Tech. Specification Surveillance: 4.8.2.4.1 DC and 4.8.2.2 AC Breaker Alignment and Power Availability ML19031B5201978-05-10010 May 1978 LER Supplemental Report for Reportable Occurrence 77-43/03L Re Inoperable No 12 S/G Channel 3 Due to Failed Pressure Transmitter ML19031B5211978-04-27027 April 1978 04/27/1978 Letter Reportable Occurrence on Excessive Concentration of Iodine in Milk Sample Collected at Environmental Sampling Location ML19031B0421978-04-17017 April 1978 LER 1978-021-03 for Salem Unit 1 Missed Surveillance of Fluoride Sample ML19031A8961978-04-17017 April 1978 LER 1978-022-01 for Salem Unit 1 Seismic Test Results for NEMA 12 Enclosures ML19031B5221978-04-11011 April 1978 LER 1978-080-03 for Salem Unit 1 Inoperability of 1B Diesel ML19031C0331978-04-0606 April 1978 04/06/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids Analysis ML19031B5231978-04-0606 April 1978 LER 1977-042-03 for Salem Unit 1 Inoperability of Channel III Pressurizer Level ML19031A8971978-04-0606 April 1978 LER 1978-018-03 for Salem Unit 1 Excessive Trip Setpoint During Functional Test on PWR Range Channel N43 ML19031A8981978-04-0505 April 1978 LER 1978-017-03 for Salem Unit 1 Tilt Ratio During Power Escalation ML19031B5261978-04-0404 April 1978 04/04/1978 Letter Reportable Occurrence on Monthly Water Quality Samples ML19031B5251978-04-0404 April 1978 04/04/1978 Letter Reportable Occurrence of Missed Sampling of River Water for Biocide 2018-01-08
[Table view] |
Text
Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark. N.J. 07101 201/622-7000 Vice President Production May 20, 1977 fJ.i~gulatory Docket File.
Mr. James P. O'Reilly D~rector of USNRC Off ice of Inspections and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 77-33/03L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 77-33/03L. This report is required within thirty (30) days of the occurrence.
CC: Director, Office of Inspection and Enforcement (30 copies)
Director, Office of Management Information and Program Control
( 3 copies)
- Report Date: 5/10/77 Occurrence Date: 4/29/77 Facility: Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Inoperable Containment Isolation Valve 1CV68 (CVCS - Charging Line Isolation Valve) .
CONDITIONS PRIOR TO OCCURRENCE:
Operational Mode 3 DESCRIPTION OF OCCURRENCE:
At 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br /> on 4/29/77, valve 1CV68 was declared inoperable due to it being stuck in the shut position. Action Statement 3.6.3.l(b) was imple-mented and 1CV69 (Series eves - Isolation) was shut and de-activated.
Investigation by Maintenance personnel revealed that the motor operator was burned up. Investigation into the operator failure revealed that the stern and wedge appeared to be jammed into the valve. The packing was removed and the stern and wedge stroked by hand. The stern and wedge would not operate smoothly. A new stern and wedge were installed and stroked by hand. The valve operation was satisfactory. A new motor operator was installed and valve stroked electrically. The testing was satisfactory. At 0410 on 4/30/77, Action Statement was terminated. At 0829, the reactor was taken critical and at 0929, the unit entered Mode
- 1. At 1300 after reviewing maintenance performed on 1CV68, Station QA informed the Shift Supervisor that a leak rate test had not been per-formed after valve disassembly, as required by Surveillance 4.6.l.2(d).
At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, the Shift Supervisor again implemented Action Statement 3.6.3.l(b) and 1CV69 was shut and de-activated. A leak rate test was performed with unsatisfactory results. 1CV68 was disassembled and the seat to wedge mating surfaces were checked. Checks showed uneven surface contact. The wedge that had been previously removed was retrieved for re-installation. Inspection showed evidence of cracks in the stellite seating surface. The valve seats appeared to be distorted. The valve seats were ground and polished. A second new wedge was obtained from spares and beca~se of seat grinding, was too small. fbr valve se~ts. A Technical Rep. from Velan Corporation was called to site. After taking dimensional checks Technical Rep. ret~rned to home office with valve wedge for rework. On 5/5/77, Technical Rep. returned to site and in-stalled reworked wedge. The valve was re-assembled and a leak rate test performed. The leak rate test was satisfactory. Action Statement 3.6.3.l(b) was terminated.
Report No. 77-33/03L - - 5/10/77 DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
The cause of the motor operator failure was over current. With the valve wedge jammed in the closed position, the attempt to open the valve caused the motor to draw excessive current damaging the motor windings.
Failure to perform the required leak rate test was caused by failure of maintenance personnel to follow the requirements of procedure Ml6E (Containment Isolation Type B and C Test) . Procedure Ml6E states that "the Maintenance Department is responsible for identifying leak retest requirements for work orders involving maintenance action on items and valves listed in Figures 3 and 4". Valve 1CV68 is listed on page 1 of Figure 4. Contrary to this requirement, no retest requirement was placed on the work order and the leak rate test was not performed. This is a licensee identified item of non-compliance.
ANALYSIS OF OCCURRENCE:
Technical Specification 3.6.3.l(b) requires that in the event of an inoperable containment isolation valve, the affected penetration be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one de-activated automatic isolation valve secured in the isolation position. 1CV69 was shut and de-activated for the term of the Action Statement. The non-compliance arose when maintenance personnel released 1CV6B to the operations department without performing a leak rate test. Operations was not aware of this requirement and returned the valve to service. The unit was taken from Mode 3 to Mode 1 before the non-compliance was identified.
This item is a violation of the Technical Specifications and Maintenance Procedure Ml6E.
CORRECTIVE ACTION:
The failed motor operator was replaced from spares. A new valve stem and wedge were installed. The valve was leak tested and stroked. All testing was satisfactory.
Corrective action for failing to perform the leak test is being handled by a series of procedure revisions. Maintenance Procedure Ml4A, General Instructions for Disassembly, Inspection and Reassembly of Valves, is being revised to include a specific precaution addressing leak testing of valves after reassembly. A list of valves requiring leak testing is also being included. Maintenance Procedure M3L, Motor Operated Valve Testing, is being revised to include a similar precaution and list.
Also, Ml4A is being changed to include a specific Shift Supervisor sign off, prior to valve disassebmly.
When procedure revisions are complete, a meeting will be held with all Maintenance Department Supervision to discuss this event and explain
~eport No. 77-33/03L ~
5/10/77 the deiails and reasons for all revisions. Corrective action should be completed by 5/30/77.
FAILURE DATA:
Valve Motor Operator Manufacturer: Limitorque Model: SMB-00 Prepared by~~-T_.~L~*~S~p_e_n_c_e_r~~~
Manager - Sa SORC Meeting No. 51-77
~~~~~~~~~
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.. LICENSEE EVENT REPORT
. ,, . CONTROL BLOCK 6
L.ICENSEE L.ICENSE EVENT NAME L.IC£NSE NUMBER TYPE TYPE REPORT REPORT CATEGORV TYl'E SOURCE OOCKET NUMBER EVENT CATE REPORT CATE ram CON"TlRJ..Qj 57 sa LlJ se l1:!.J I 0 I 5 I 0 I -"I 0 I 2 I 7 l 2 I I0 I 4 I2 I9 17 17 I I0 15 I 1 l 0 I7 I ~
so 61 sa es 74 15 EVENT DESCRIPTION
@]JI. During Mode 3. 1CV68 (CVCS - Containment Isolation Vlv) was declared in- 1 7 89 80
~ o erable. lCV69, series isolation valve was o erable. Valve 1CV68 was 7 8 9
@El* returned to service after repairs without required leak rate test. Pro-7 8
@Jill cedures have been revised to include requirement for leak rate test. I 7 8 9 ao (ill] (77-33/03L) 7 8 9 CAUSE P1'11ME COMPONENT COMPONENT ao SYSTEM COCE coce: COMPONENT COOE SUPPl..IER MANUFACTURER VIOLATION
@TIJ!SIDI l£:.l I VI Al LIV I E.Jl:U Lbl ILi Z 10 10 I LXJ 1 ag 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION
~I Valve being.jammed in shut position caused motor to draw excessive l*
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9 current.
Personnel error caused non-compliance to leak rate requirement 1 so UEa~9------------------------------.,....-------------------------------------~----------eo....J 1
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8i so NAMe: ________ T_.__L __.--'S=p...;;e:;,.:;n;.::.c=.:::e:;,.:;r=------------- PHONE: ( 609) 3 6 5-7 0 0 0 Ext. Salem-52