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| | issue date = 10/18/1973 | | | issue date = 10/18/1973 |
| | title = Letter Reporting a 10/09/1973 Occurrence Relating to M0-3-1301-1 Valve in the Isolation Condenser System Failed to Operate Correctly - Dresden Unit 3 | | | title = Letter Reporting a 10/09/1973 Occurrence Relating to M0-3-1301-1 Valve in the Isolation Condenser System Failed to Operate Correctly - Dresden Unit 3 |
| | author name = Worden W P | | | author name = Worden W |
| | author affiliation = Commonwealth Edison Co | | | author affiliation = Commonwealth Edison Co |
| | addressee name = Giambusso A | | | addressee name = Giambusso A |
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| =Text= | | =Text= |
| {{#Wiki_filter:CommonwealAdison One First National Sa. Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 WPW Ltr.#782-73 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C. 20545 50-249 Dresden Nuclear Power Station R. R. #1 Morris, Illinois October 18, 1973 SU.BJECT:. LICENSE DPR-25, DRESDEN NUCLEAR POWER STATION, UNIT #3, SECTION 6.6.B.2 OF THE TECHNICAL SPECIFICATIONS ISOLATION CONDENSER VALVE FAILURE | | {{#Wiki_filter:CommonwealAdison One First National Sa. Chicago, Illinois Address Reply to: Post Office Box 767 50-249 Chicago, Illinois 60690 |
| | ~egutatofy FHe Cy. |
| | WPW Ltr.#782-73 Dresden Nuclear Power Station R. R. #1 Morris, Illinois October 18, 1973 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C. 20545 SU.BJECT:. LICENSE DPR-25, DRESDEN NUCLEAR POWER STATION, UNIT #3, SECTION 6.6.B.2 OF THE TECHNICAL SPECIFICATIONS ISOLATION CONDENSER VALVE FAILURE |
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| ==References:== | | ==References:== |
| 1) Notification Qf Region III of ABC Regulatory Operations Telephone: F. Maura, 1100 hours on October 10, 1973 Telegram: Mr. Keppler, 1100. hours on-October 10, 1973 | | : 1) Notification Qf Region III of ABC Regulatory Operations Telephone: F. Maura, 1100 hours on October 10, 1973 Telegram: Mr. Keppler, 1100. hours on-October 10, 1973 * |
| * 2) Drawings M-28 Dresden s*tation P & ID.
| | : 2) Drawings M-28 Dresden s*tation P & ID. |
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| ==Dear Mr. Giambusso:== | | ==Dear Mr. Giambusso:== |
| . This letter is .to report a condition relating to the operation of the unit at 1450 hours; on October 9, 1973. At this time M0-3-1301-:1 valve in the isolation condensez:: system failed to operate correctly. This -malfunction is contrary to. section 3.5.E.l_of the Technical Specifications which requires that the isolation condenser be operable when reactor pressure is above 90 psig and irradiated fuel is in the vessel. PROBLEM Following performance of Isolation Condenser high steam flow, and high condensate flow surveillance, valve M03-1301-l failed to open when the isolation was reset. The supply breaker for the M03*1301-l valve was found tripped. It was reset.and the valve then tested FHe Cy. At the time of the failure, the reactor was in the "Run". mode and .. thewi power was-2244. *-The was -ope-rs-ting at-a steady . -. electric.-load of 740 megawatts. Reactor pressure was 993 psig. (\f
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| *** .. Mr. A. Giambusso e October 18, 1973 'INVESTIGATION An investigation into the* problem failed to provide a cause for the breaker trip. As stated previously, the problem corrected itself once the breaker was reset. This problem has occurred on other valve breakers and is presently under investigation. For the present status of the breaker investigation, see Dresden Station's report of a of valve M03-1501-20B October 1, 1973. CORRECTIVE ACTION The immediate corrective action taken was to reset the breaker trip and attempt a second valve* operation. The second at.tempt to operate the valve proved to be successful with the valve operating as designed. Also, this type of breaker failure. has been under* investigation and at this time a cause for the breaker trips has* npt been found. The investigation of this type of failure -will continue until the problem has been solved. Any further correct.ive actions will be based on the finds of the investigation. EVALUATION During the failure of the M03-1301-l valve," the safety of the plant and public was not iri jeopardy. With the valve failing closed, it assurred primary containment integrity. However, with the valve the isolation condenser system would be inoperable. At the time of the failure, the high pressure core injection (HPCi) and Auto Blowdown systems were operational. Continued operation of the plant was considered safe because of .the short time valve 3-1301-1 was not operational the operational status of the high pressure injection and auto blowdown systems. WPW:dQ S.incerely, "3'.Rs-Jl j. W. P. Worden Superi11tendent | | . This letter is .to report a condition relating to the operation of the unit at 1450 hours; on October 9, 1973. At this time M0-3-1301-:1 valve in the isolation condensez:: system failed to operate correctly. This |
| }} | | - malfunction is contrary to. section 3.5.E.l_of the Technical Specifications which requires that the isolation condenser be operable when reactor pressure is above 90 psig and irradiated fuel is in the vessel. |
| | PROBLEM Following performance of Isolation Condenser high steam flow, and high condensate flow surveillance, valve M03-1301-l failed to open when the isolation was reset. The supply breaker for the M03*1301-l valve was found tripped. It was reset.and the valve then tested satisfactorily~ |
| | At the time of the failure, the reactor was in the "Run". mode and .. thewi power was- 2244. megawatts~ *-The u~it was -ope-rs-ting at- a steady . -. |
| | electric.- load of 740 megawatts. Reactor pressure was 993 psig. |
| | (\f |
| | |
| | *** .. ;.....,.?*'"'~ |
| | Mr. A. Giambusso e October 18, 1973 |
| | 'INVESTIGATION An investigation into the* problem failed to provide a cause for the breaker trip. As stated previously, the problem corrected itself once the breaker was reset. This problem has occurred on other valve breakers and is presently under investigation. For the present status of the breaker investigation, see Dresden Station's report of a malfun~tion of valve M03-1501-20B ~n October 1, 1973. |
| | CORRECTIVE ACTION The immediate corrective action taken was to reset the breaker trip and attempt a second valve* operation. The second at.tempt to operate the valve proved to be successful with the valve operating as designed. |
| | Also, this type of breaker failure. has been under* investigation and at this time a cause for the breaker trips has* npt been found. The investigation of this type of failure -will continue until the problem has been solved. Any further correct.ive actions will be based on the finds of the investigation. |
| | EVALUATION During the failure of the M03-1301-l valve," the safety of the plant and public was not iri jeopardy. With the valve failing closed, it assurred primary containment integrity. However, with the valve closed~ |
| | the isolation condenser system would be inoperable. At the time of the failure, the high pressure core injection (HPCi) and Auto Blowdown systems were operational. |
| | Continued operation of the plant was considered safe because of |
| | .the short time valve 3-1301-1 was not operational an~ the operational status of the high pressure cor~ injection and auto blowdown systems. |
| | S.incerely, "3'.Rs-Jl j. lM~ |
| | W. P. Worden Superi11tendent WPW:dQ}} |
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Category:Letter
MONTHYEARML24303A0712024-11-0404 November 2024 Letter to K. Meshigaud, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0992024-11-0101 November 2024 Lett to R. Carter, Principal Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0152024-11-0101 November 2024 Letter to C. Harper, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1102024-11-0101 November 2024 Letter to R. Gasco, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1442024-11-0101 November 2024 Letter to V. Kitcheyna, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0532024-11-0101 November 2024 Letter to J. Greendeer, President Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0492024-11-0101 November 2024 Letter G. Kakkak, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0892024-11-0101 November 2024 Letter to M. J. Wesaw, Chair Request to Initiate Section 106 Consultation for SLR of DNP Station RS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision ML24303A0172024-11-0101 November 2024 Letter to B. Peters, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0432024-11-0101 November 2024 Letter to E. Elizondo, Sr. Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0252024-11-0101 November 2024 Letter to R. Blanchard Tribal Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0552024-11-0101 November 2024 Letter to J. Keys, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0472024-11-0101 November 2024 Letter to G. Cheatham, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0202024-11-0101 November 2024 Letter to C. Chavers, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1462024-11-0101 November 2024 Letter to W. Gravelle, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1352024-11-0101 November 2024 Letter to T. Rhodd, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 ML24303A1172024-11-0101 November 2024 Letter to R. Yob, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0132024-11-0101 November 2024 Letter to B. Barnes, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0512024-11-0101 November 2024 Letter to J. Barrett, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0242024-11-0101 November 2024 Letter to D. Kaskaske, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1422024-11-0101 November 2024 Letter to V. Jefferson, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0602024-11-0101 November 2024 Letter to J. R. Shotton, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0272024-10-31031 October 2024 NRC Letter to C. Mayer Illinois SHPO Request to Initiate Section 106 Consultation for Subsequent License Renewal of Units 2 and 3 ML24291A0202024-10-31031 October 2024 NRC Letter to J. Loichinger Achp Request for Comments Concerning the Environmental Review of DNPS Units 2 and 3 Subsequent License Renewal Application IR 05000237/20240032024-10-29029 October 2024 Integrated Inspection Report 05000237/2024003 and 05000249/2024003 RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-102, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-5912024-10-21021 October 2024 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591 RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24225A2132024-09-26026 September 2024 Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval ML24253A0942024-09-23023 September 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID L-2024-Sle-0002) (Docket Numbers: 50-237 and 50-249) SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual Effluent Release Report ML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000237/20244022024-09-19019 September 2024 – Security Baseline Inspection Report 05000237/2024402 and 05000249/2024402 - (Public) ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2152024-09-16016 September 2024 Confirmation of Initial License Examination ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 ML24215A2912024-08-14014 August 2024 Request for Withholding Information from Public Disclosure Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000237/LER-2023-001, HPCI Inoperable Due to Air Void Accumulation2024-01-19019 January 2024 HPCI Inoperable Due to Air Void Accumulation ML20135G7442020-05-14014 May 2020 Final ASP Analysis - Dresden 2 (LER 237-90-006) 05000249/LER-2017-0012017-12-27027 December 2017 Unit 3 Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak, LER 17-001-01 for Dresden Nuclear Power Station, Unit 3 Regarding Unit 3 Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak ML17252B5052017-11-0303 November 2017 LER 77-050/03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling ML17252A3262017-10-21021 October 2017 LER 77-040/03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position ML17252B4922017-08-28028 August 2017 LER 78-028/01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction 05000237/LER-2016-0032017-05-26026 May 2017 Control Room Emergency Ventilation System Charcoal Filter Bank Failure to meet the Methyl Iodide Penetration Acceptance Criteria, Dresden Nuclear Power Station, Units 2 and 3, Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to meet the Methyl Iodide Penetration Acceptance Criteria ML17153A0342017-05-26026 May 2017 Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria 05000237/LER-2016-0042017-01-0909 January 2017 Reactor Building Differential Pressure Less than Technical Specification Requirement, LER 16-004-00 for Dresden Nuclear Power Station, Unit 2, Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement 05000249/LER-2016-0012016-08-25025 August 2016 Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire, LER 16-001-00 for Dresden Nuclear Power Station Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire 05000237/LER-2016-0022016-07-15015 July 2016 Unit 2 HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability, LER 16-002-00 for Dresden Nuclear Power Station, Unit 2 Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability 05000237/LER-2016-0012016-04-0808 April 2016 Secondary Containment Differential Pressure Transient, LER 16-001-00 for Dresden Nuclear Power Station, Unit 2 and 3 Regarding Secondary Containment Differential Pressure Transient 05000249/LER-2015-0012016-01-22022 January 2016 Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value, LER 15-001-01, Dresden, Unit 3 Main Steam Line Flow Switched Found Outside Tech Spec Allowed Value ML1015505692009-07-24024 July 2009 Letter LS-AA-1 25-1001, Elevated Tritium Values Identified in 2 Storm Drains Due to Through-Wall Leaks in Underground Piping for Dresden Units 2 and 3. ML0602404072004-05-0505 May 2004 Final Precursor Analysis - Dresden Unit 3 - Unit 3 Scram Due to Loss of Offsite Power and Subsequent Inoperability of the Standby Gas Treatment System for Units 2 and 3 ML0234501722002-12-0202 December 2002 LER 89-029-05, Dresden Unit 2, Elevated HPCI Discharge Piping Temperature Due to Reactor Feedwater System Back Leakage ML17252B5391981-06-10010 June 1981 LER 81-034/03L-0 for Dresden, Unit 2 Re J-3 CRD Was Tested for Overtravel. the Overtravel Alarm Came Up and Rod Position Indication Was Lost ML17252B5411981-06-0808 June 1981 LER 81-030/01T-0 for Dresden, Unit 2 Re Operator Noticed the HPCI Steam Line Was Cold and Filled with Water. the HPCI System Was Declared Inoperable ML17252B5401981-06-0505 June 1981 LER 81-024/03L-0 for Dresden, Unit 2 Re While Conducting Routine Review of Surveillance, It Was Found That the Monthly Surveillance Required by Tech. Spec. 4.4.c.1 for Standby Liquid Control Tank Sampling Was Three Days Overdue ML17252B5271981-06-0303 June 1981 LER 81-023/03L-0 for Dresden, Unit 2 Re While Running HPCI Pump Test, the Operator Observed Torus Wide Range Level Instrument Reading 0 Inches and Narrow Range Level Instrument Reading, About - 2 Inches and Oscillating ML17252B5281981-04-14014 April 1981 LER 81-015/03L-0 for Dresden, Unit 2 Re the Fire Marshall Discovered That the Heat Detectors Were Not Functionally Tested within the 6 Month Interval Required by Tech. Spec. 4.12.A.1 ML17252B5291981-03-23023 March 1981 LER 81-011-03L-0 for Dresden, Unit 2 Re Observed Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems or Engineered Safe ML17252B5301981-02-20020 February 1981 LER 81-080/031-0 for Dresden, Unit 2 Re Abnormal Degradation of Systems Other than Those Specified in Item B.1.e Above Designed to Contain Radioactive Material Resulting from the Fission Process ML17252B5321981-02-17017 February 1981 LER 81-070/03L for Dresden, Unit 2 Re While Conducting Steam Line Area Temperature Switch Calibration Surveillance, Temperature Switch TS 2-261-180 Failed to Trip ML17252B5331981-02-0202 February 1981 LER 81-020/03L-0 for Dresden, Unit 2 Re During Refueling Outage LPCI Test Spray Valve Failed to Shut Electrically, One Set of Thermal Contacts Would Not Reset ML17252B5341981-01-23023 January 1981 LER 80-049/03L-0 for Dresden, Unit 2 Re at Completion of Secondary Containment Leak Rate Test the Reactor Building Ventilation Isolation Valve 2A-5742 Would Not Open ML17252B5351981-01-23023 January 1981 LER 80-050/03L-0 for Dresden, Unit 2 Re the 1501-62D Pressure Switch Actuated at 44.2 Inches of Water Increasing, Tech. Spec. Limit Is Less than or Equal to 41.6 Inches of Water Increasing ML17252B5371980-12-30030 December 1980 LER 80-046-00 for Dresden 2 Regarding a Failure to Receive CRD Volume During a Reactor Scram ML17252B5361980-12-29029 December 1980 LER 80-046/03L-0 for Dresden, Unit 2 Re Conditions Leading to on Operation in a Degraded Mode Permitted by a Limiting Condition for Operation or Plant Shutdown Required by a Limiting Condition for Operation ML17252B5381980-12-0303 December 1980 LER 80-043/03L-0 for Dresden, Unit 2 Re Surveillance Testing of the Condenser Low Vacuum Switches, Pressure Switch 2-503D Was Found to Have a Trip Point of 22.85 Inches Hg ML17252B5431980-11-12012 November 1980 LER 80-041/03L-0 for Dresden, Unit 2 Re Reactor Building Vent and Refueling Floor Rad Monitor Surveillance (DCP 2007-12) Was Performed ML17252B5421980-11-12012 November 1980 LER 80-042/03L-0 for Dresden, Units 2 and 3 Re That Technical Staff Personnel Revealed That the Ultrasonic Testing of the Scram Discharge Volume Was Not Performed During the 1500-2300 Shift ML17252B1841980-10-31031 October 1980 LER 80-40/01T-0 for Dresden Unit 3 Regarding Failure of the HPCI Inboard Steam Supply Valve to Open ML17252B5441980-10-29029 October 1980 LER 80-039/03X-1 for Dresden, Unit 2 Re HPCI Inboard Steam Supply Valve Opened and Had a Dual Light Indication ML17252B5451980-10-23023 October 1980 LER 79-017-01X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety ML17252B5461980-10-0808 October 1980 LER 80-016/01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line ML17252B5471980-10-0707 October 1980 LER 80-036/03L-0 for Dresden, Unit 2 Re Discovery That the Six Month Functional Test Required by Tech. Spec. 4.12.A.1 of the Cardox System Heat Detectors Was Not Performed within the Allowable Surveillance Interval ML17252B5481980-10-0101 October 1980 LER 80-033/03L-0 for Dresden, Unit 2 Re the Frequency of Water Addition to the Torus Increased. Leak Rate Tests Indicated a Leak in the 2B LPCI Heat Exchanger ML17252B1861980-08-22022 August 1980 LER 80-032/03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block ML17252B5501980-08-19019 August 1980 LER 80-027/03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator ML17252B5161980-08-14014 August 1980 LER 80-024/03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d ML17252B1881980-08-0404 August 1980 LER 80-030/03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds ML17252B1901980-06-13013 June 1980 LER 80-023/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches ML17252B1911980-06-13013 June 1980 LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches ML17252B1921980-06-10010 June 1980 LER 80-025/03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1 ML17252B5521980-06-0505 June 1980 LER 80-017/03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close ML17252B1931980-06-0303 June 1980 LER 80-002/03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close ML17252B5531980-05-27027 May 1980 LER 80-015/03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33A Was Found Inoperable During Routine Operability Surveillance ML17252B1941980-05-27027 May 1980 LER 80-022/03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125 ML17252B1951980-05-0808 May 1980 LER 80-021/01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operability 2024-01-19
[Table view] |
Text
CommonwealAdison One First National Sa. Chicago, Illinois Address Reply to: Post Office Box 767 50-249 Chicago, Illinois 60690
~egutatofy FHe Cy.
WPW Ltr.#782-73 Dresden Nuclear Power Station R. R. #1 Morris, Illinois October 18, 1973 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C. 20545 SU.BJECT:. LICENSE DPR-25, DRESDEN NUCLEAR POWER STATION, UNIT #3, SECTION 6.6.B.2 OF THE TECHNICAL SPECIFICATIONS ISOLATION CONDENSER VALVE FAILURE
References:
- 1) Notification Qf Region III of ABC Regulatory Operations Telephone: F. Maura, 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on October 10, 1973 Telegram: Mr. Keppler, 1100. hours on-October 10, 1973 *
- 2) Drawings M-28 Dresden s*tation P & ID.
Dear Mr. Giambusso:
. This letter is .to report a condition relating to the operation of the unit at 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br />; on October 9, 1973. At this time M0-3-1301-:1 valve in the isolation condensez:: system failed to operate correctly. This
- malfunction is contrary to. section 3.5.E.l_of the Technical Specifications which requires that the isolation condenser be operable when reactor pressure is above 90 psig and irradiated fuel is in the vessel.
PROBLEM Following performance of Isolation Condenser high steam flow, and high condensate flow surveillance, valve M03-1301-l failed to open when the isolation was reset. The supply breaker for the M03*1301-l valve was found tripped. It was reset.and the valve then tested satisfactorily~
At the time of the failure, the reactor was in the "Run". mode and .. thewi power was- 2244. megawatts~ *-The u~it was -ope-rs-ting at- a steady . -.
electric.- load of 740 megawatts. Reactor pressure was 993 psig.
(\f
Mr. A. Giambusso e October 18, 1973
'INVESTIGATION An investigation into the* problem failed to provide a cause for the breaker trip. As stated previously, the problem corrected itself once the breaker was reset. This problem has occurred on other valve breakers and is presently under investigation. For the present status of the breaker investigation, see Dresden Station's report of a malfun~tion of valve M03-1501-20B ~n October 1, 1973.
CORRECTIVE ACTION The immediate corrective action taken was to reset the breaker trip and attempt a second valve* operation. The second at.tempt to operate the valve proved to be successful with the valve operating as designed.
Also, this type of breaker failure. has been under* investigation and at this time a cause for the breaker trips has* npt been found. The investigation of this type of failure -will continue until the problem has been solved. Any further correct.ive actions will be based on the finds of the investigation.
EVALUATION During the failure of the M03-1301-l valve," the safety of the plant and public was not iri jeopardy. With the valve failing closed, it assurred primary containment integrity. However, with the valve closed~
the isolation condenser system would be inoperable. At the time of the failure, the high pressure core injection (HPCi) and Auto Blowdown systems were operational.
Continued operation of the plant was considered safe because of
.the short time valve 3-1301-1 was not operational an~ the operational status of the high pressure cor~ injection and auto blowdown systems.
S.incerely, "3'.Rs-Jl j. lM~
W. P. Worden Superi11tendent WPW:dQ