|
|
(5 intermediate revisions by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 04/17/1973 | | | issue date = 04/17/1973 |
| | title = Letter Reporting a 04/09/1973 Occurrence in Which Main Steam Line Pressure Switch PSL-3-261-30A's Setting Was Found to Have Drifted -Dresden Unit 3 | | | title = Letter Reporting a 04/09/1973 Occurrence in Which Main Steam Line Pressure Switch PSL-3-261-30A's Setting Was Found to Have Drifted -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 |
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:50-249 Commonwealth_ Edison Company ONE FIRST NATIONAL PLAZA* CHICAGO. ILLINOIS Address Reply to' POST OFFICE BOX 767 *CHICAGO, ILLINOIS 60690 WPW Ltr. #308-73 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensiiig* U. S. Atomic Ehergy Commission Washington, D .c. 20545 _ Dresden Nuclear Power station R. R. #1 Morris, Illinois 60450 April 17, 197.3 SUBJEX::T: UCENSE DPR . 25, DRESDEN NUCLEAR POWER STATION, UNIT #3, SFCTION 6.6.B.3 OF.THE TEX::HNICAL SPECIFICATIONS. | | {{#Wiki_filter:50-249 Commonwealth_ Edison Company ONE FIRST NATIONAL PLAZA* CHICAGO. ILLINOIS Address Reply to' POST OFFICE BOX 767 *CHICAGO, ILLINOIS 60690 Dresden Nuclear Power station R. R. #1 Morris, Illinois 60450 WPW Ltr. #308-73 April 17, 197.3 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensiiig* |
| | U. S. Atomic Ehergy Commission Washington, D.c. 20545 _ |
| | SUBJEX::T: UCENSE DPR . 25, DRESDEN NUCLEAR POWER STATION, UNIT #3, SFCTION 6.6.B.3 OF.THE TEX::HNICAL SPECIFICATIONS. |
|
| |
|
| ==Dear Mr. Giambusso:== | | ==Dear Mr. Giambusso:== |
| This is to report a condition:-relating to the operation or the Unit in which on April 9, 1973, a main steam line pressure switch setting was found to have drifted. Pressure switch PSL-3-261-.30A was found tripping at 816 PSI which .is below the Technical Specification limit of' 850 PSI as described in Section .3.2.a. PROBLEM AND INVESTIGATION During a slirveillance inspection of* t_he -main steam line low pressure switches the set poi.iit for Barksdale switch 3-261-.30A was found to have drifted *to 816 The switch had been previously set at 871 PSI. The purpose of the pressure switch is to sense a drop in pressure due to a break in a ins.in steam line, and initiate a group I isolation. The electrical arrangement for a group I isolation initiation from a main steam line break is a twice logic. Therefore, it would have required two switch failures to prevent an isolation at 850 PSI. ../ Had a maiD steam line break occurred While the pressure setting of the PSL-3-261-JOA switch was 816 PSI all the main steam isolation valves would have closed at 850 PSI. Thus, the failure of switch .3-261-.30A did not present a hazard to.the public safety since an isolation would have occurred at 850 PSI as designed. 2602 CORRECTIVE ACTION ---The immediate corrective action was to reset the pressure switch setting to 872 PSI. The PSL-3-261-JOA will be replaced prior to the* unit-startup due to its failure history {Reference our letter dated December 29, 1972). | | |
| * In addition, this switch type is presently under investigation by the manufacturer and the Station Instrument Department to determine the cause of set point drift. Fd;nciings of the investigation will dictate future corrective actions. ;f-"* .. ,:.;. ',: . -* cc: _ WPtl , -Sincerely, ,. -'11' *** : -/) ""' W. .P. Worden .fW '< Superintendent ,_ . '. "" '" . ' : ..... '::. .. .... ., ' \}} | | This is to report a condition:-relating to the operation or the Unit in which on April 9, 1973, a main steam line pressure switch setting was found to have drifted. Pressure switch PSL-3-261-.30A was found tripping at 816 PSI which |
| | .is below the Technical Specification limit of' 850 PSI as described in Section |
| | .3.2.a. |
| | PROBLEM AND INVESTIGATION During a slirveillance inspection of* t_he -main steam line low pressure switches the set poi.iit for Barksdale switch 3-261-.30A was found to have drifted |
| | *to 816 PSI~ The switch had been previously set at 871 PSI. The purpose of the pressure switch is to sense a drop in pressure due to a break in a ins.in steam line, and initiate a group I isolation. The electrical arrangement for a group I isolation initiation from a main steam line break is a one-out-of-two-twice logic. Therefore, it would have required two switch failures to prevent an isolation at 850 PSI. |
| | ../ |
| | Had a maiD steam line break occurred While the pressure setting of the PSL-3-261-JOA switch was 816 PSI all the main steam isolation valves would have closed at 850 PSI. Thus, the failure of switch .3-261-.30A did not present a hazard to.the public safety since an isolation would have occurred at 850 PSI as designed. |
| | 2602 |
| | |
| | CORRECTIVE ACTION The immediate corrective action was to reset the pressure switch setting to 872 PSI. The PSL-3-261-JOA swit~h will be replaced prior to the* |
| | unit-startup due to its failure history {Reference our letter dated December 29, 1972). |
| | * In addition, this switch type is presently under investigation by the manufacturer and the Station Instrument Department to determine the cause of set point drift. Fd;nciings of the investigation will dictate future corrective actions. |
| | ;f-"* |
| | Sincerely, |
| | ~~- JJ(,(~ ,. - |
| | /) ""' W. .P. Worden |
| | .fW '< Superintendent |
| | ~ |
| | . '11' * ** : - |
| | ~' |
| | ~. |
| | .'. ~- "" '" . ' :..... |
| | -* '::. ~ |
| | cc: _WPtl ttr~* F~le |
| | \ |
| | ,-}} |
|
---|
Category:Letter
MONTHYEARML24270A0332024-09-20020 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 IR 05000237/20230052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2023005; 05000249/2024005) 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 IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, Safety Limit MCPR ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24158A0012024-05-22022 May 2024 License Amendment Request to Adopt TSTF-564 (EPID L-2023-LLA-0120) Illinois State Concurrence ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24135A0722024-05-10010 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report ML24134A1132024-05-0808 May 2024 Retraction: LER 2303-001-00 for Dresden Nuclear Power Station, Unit 2, HPCI Inoperable Due to Air Void Accumulation ML24129A1352024-05-0808 May 2024 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-59 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24092A3412024-05-0101 May 2024 SLRA - Receipt and Availability - Letter IR 05000237/20240012024-05-0101 May 2024 Integrated Inspection Report 05000237/2024001 & 05000249/2024001 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 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 ML24127A0982024-04-30030 April 2024 Radioactive Effluent Release Report ML24120A2032024-04-29029 April 2024 Operator Licensing Exam Approval - Dresden Nuclear Power Station, May 2024 IR 05000237/20244012024-04-18018 April 2024 – Security Baseline Inspection Report 05000237/2024401 and 05000249/2024401 ML24108A0082024-04-17017 April 2024 Application for Renewed Operating License RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. 2024-09-06
[Table view] Category:Note to File incl Telcon Record
MONTHYEARML17252B4162017-09-0909 September 2017 Letter Confirming a Conversation Concerning the Report of an Empty Spent Fuel Shipping Cask Which Had Some Areas of Removable Surface Contamination ML17252B4142017-09-0909 September 2017 Letter Confirming a Conversation Concerning the Failure of HPCI Valve Mo 2-2301-8 During a Maintenance Outage and the Discovery of a Broken Stem ML0528500652005-10-24024 October 2005 Minutes of Conference Call Regarding Dresden MSSV Setpoint Tolerance (Response to License Condition 4 from July 30, 2004 Amendment) ML0331002702002-08-19019 August 2002 Note to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331002432002-08-0707 August 2002 Note to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331001982002-05-0808 May 2002 Noie to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331001842002-05-0707 May 2002 Note to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331001972002-05-0707 May 2002 Note to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331001732002-04-25025 April 2002 Note to Telephone Conversation - Robert O'Connell - NMSS 2002-A-0002 ML17252B4171976-12-0606 December 1976 Letter Confirming a 12/06/1976 Conversation Concerning the Receipt of an Empty Spent Fuel Shipping Cask Which Had Some Areas of Removeable Surface Contamination ML17252B4181976-12-0303 December 1976 Letter Confirming a Conversation Concerning Information Received That Indicates the R.W.M. Should Remain in Service or a Qualified Person Must Verify All Control Rod Movement Through 20% Power ML17252B4191976-12-0202 December 1976 Letter Confirming a 12/02/1976 Conversation Concerning Receipt of an Empty Spent Fuel Shipping Cask from GE Morris Operation Which Had Some Areas of Removable Surface Contamination ML17252B4571975-11-17017 November 1975 Letter Confirming a Conversation Concerning Quarterly Closure Timing of IC Main Steam Isolation Valve in Which the Closure Time Was Found at 2.7 Seconds ML17252B4581975-11-0404 November 1975 Letter Confirming a Conversation Concerning Discovery of High Level in the Torus While Running a HPCI Surveillance Check ML17252A4461975-07-31031 July 1975 Incident Notification Concerning Location of Broken Tack Welds on Jet Pump Restrainer Clamp Bolt Keepers During Tv Camera Examination of Unit 3 Jet Pumps - Dresden Unit 3 ML17252A9121975-04-25025 April 1975 Letter Confirming a 04/25/1975 Conversation Concerning Excessive Leakage Through Torus to Drywell Vacuum Breaker 3-1601-32B During Refuel Outage Local Leak Testing - Dresden Unit 3 ML17252A9131975-04-23023 April 1975 Letter Confirming a 04/23/1975 Conversation Concerning Failure of Feedwater Check Valves, 3-220-58A and 62A, and 3A Feedwater Line to Pass Local Leak Rate Test During Refuel Outage Surveillance - Dresden Unit 3 ML17252A7871975-03-19019 March 1975 Note to Confirm a Conversation Concerning Routine Main Steamline High Radiation Monitor Surveillance in Which the a and B Monitors Were Found to Have Set Points in Excess of Technical Specification Values - Dresden Unit 3 ML17252A7891975-03-19019 March 1975 Note to Confirm a Conversation Concerning Routine Main Steamline High Radiation Monitor Surveillance in Which the a and B Monitors Were Found to Have Set Points Exceeding the Techspec Value of 3 Times Background - Dresden Unit 3 ML17252A8241975-02-18018 February 1975 Note to Confirm a Conversation Concerning Discovery of a Leaking Containment Inerting Isolation Valve A03-1601-21 During Local Leak Rate Testing - Dresden Unit 3 ML17252A8251975-02-18018 February 1975 Note Confirming a Conversation Concerning Failure of Bergen Patterson Piping Restraint Number 19 on the Unit 3 HPCI Main Steam Line in the Dry-Well - Dresden Unit 3 ML17252B0291975-02-10010 February 1975 Letter Confirming a 02/10/1975 Conversation Concerning a Leak in a 3/4 Inch Vent Line at Weld on 3C Reactor Feed Pump Casing - Dresden Unit 3 ML17252A8231975-02-10010 February 1975 Note to Confirm a Conversation Concerning a Leak in a 3/4 Inch Vent Line at a Well on 3C Reactor Feed Pump Casing - Dresden Unit 3 ML17252A8371975-01-0707 January 1975 Note Confirming a Conversation Concerning a Xenon Transient Experienced on Unit 3 During a Control Rod Pattern Alteration - Dresden Unit 3 ML17252B0281975-01-0606 January 1975 Letter Confirming a 01/06/1975 Conversation Concerning Excess Chloride Content in Reactor Coolant Water During an Extended Reactor Cleanup System Maintenance Outage - Dresden Unit 3 ML17252A8321975-01-0606 January 1975 Note to Confirm a Conversation Concerning Excess Chloride Content in Unit 3 Reactor Coolant Water During a Extended Reactor Cleanup System Maintenance Outage - Dresden Unit 3 ML17252A4841974-12-0606 December 1974 Letter Confirming a 12/02/1974 Conversation Concerning the Discovery of Minor Leaks on the Minimum Flow Lines for 3A and 3B Reactor Feed Pumps - Dresden Unit 3 ML17252A4911974-10-23023 October 1974 Letter Confirming a 08/28/1974 Conversation Concerning a Failure to Maintain the 3A Core Spray Discharge Header in a Filled Condition - Dresden Unit 3 ML17252A4951974-10-0404 October 1974 Letter Confirming a 10/04/1974 Conversation Concerning the Discovery of DPI83-2352 with a Setpoint Greater than the Technical Specification ML17252A4971974-09-30030 September 1974 Letter Confirming a 09/30/1974 Conversation Concerning Discovery of Lits 3-263-72A and the Set Points Exceeding Technical Specifications ML17252A5001974-09-24024 September 1974 Letter Confirming a 09/24/1974 Conversation Concerning a Through Wall Crack Discovered on Torus Purge Inlet Line 3-8506-18 - Dresden Unit 3 ML17252A5011974-09-24024 September 1974 Letter Confirming a 09/21/1974 Conversation Concerning a Minor Leak from Feed Water Pressure Tap 3241-12A - Dresden Unit 3 ML17252A5051974-09-0909 September 1974 Letter Confirming a 09/09/1974 Conversation Concerning Failure of E Tip Valve to Close - Dresden Unit 3 ML17252B0311974-08-28028 August 1974 Letter Confirming a 08/23/1974 Conversation Concerning a Failure to Maintain the 3A Core Spray Discharge Header in a Filled Condition as Required by Technical Specifications - Dresden Unit 3 ML17252A5071974-08-14014 August 1974 Letter Confirming a 08/08/1974 Conversation Concerning a Failure of the Solenoid Operated Isolation Valve Associated with the 3B Traversing Encore Probe to Close - Dresden Unit 3 ML17252A5081974-08-0606 August 1974 Letter Confirming a 07/26/1974 Conversation Concerning Failure of the Seat Material of the Air Operated Primary Containment Isolation Valve A03-1601-22 - Dresden Unit 3 ML17252A5111974-07-29029 July 1974 Letter Confirming a 07/29/1974 Conversation Concerning Failure of the Seat Material of Air Operated Isolation Valve AO-3-1601-21 - Dresden Unit 3 ML17252A5121974-07-29029 July 1974 Letter Confirming a 07/26/1974 Conversation Concerning the Failure of the Seat Material of Air Operated Primary Containment Valve A03-1601-22 - Dresden Unit 3 ML17252A5151974-07-23023 July 1974 Letter Confirming a 07/19/1974 Conversation Concerning the Discovery of HPCI High Steam Flow Isolation Switch DPIS 3-2352 to Be Out of Flex - Dresden Unit 3 ML17252A5161974-07-19019 July 1974 Letter Confirming a 07/19/1974 Conversation Concerning Discovery of HPCI High Steam Flow Isolation Switch DPIS 3-2352 to Be Out of Flex - Dresden Unit 3 ML17252A5171974-07-16016 July 1974 Letter Confirming a 07/16/1974 Conversation Concerning the Failure to Reach the Required Containment Oxygen Concentration of 4 Percent within 24 Hours of Placing Mode Switch in Run Position - Dresden Unit 3 ML17252A5271974-07-0505 July 1974 Letter Confirming a 05/24/1974 Conversation Concerning the Discovery of a Set Point Drift of L.I.T.S. 3-263-72A Beyond the Technical Specification - Dresden Unit 3 ML17252A5261974-06-24024 June 1974 Letter Confirming a 06/24/1974 Conversation Concerning a Failure of the Air Supply to the Feed Water Regulating Valve on 06/23/1974 - Dresden Unit 3 ML17252A5291974-06-24024 June 1974 Letter Confirming a 06/24/1974 Conversation Concerning a Failure of the Air Supply to the Feed Water Regulating Valve on 06/23/1974 - Dresden Unit 3 ML17252A5251974-06-17017 June 1974 Letter Confirming a 06/17/1974 Conversation Concerning the Failure of Main Steam Drain Valve M03-220-2 to Operate Properly on 05/22/1974 - Dresden Unit 3 ML17252A5361974-06-17017 June 1974 Letter Confirming a 06/17/1974 Conversation Concerning a Failure of Main Steam Valve M03-220-2 to Operate on 05/22/1974 - Dresden Unit 3 ML17252A5241974-06-12012 June 1974 Letter Confirming a 06/12/1974 Conversation Concerning the Discovery of 2 Reactor High Pressure Scram Switches (PS-3-263-55A and C) with Set Points Above the Technical Specification Limit - Dresden Unit 3 ML17252A5231974-06-11011 June 1974 Letter Confirming a 06/11/1974 Conversation Concerning a Small Leak in Line 3-3037B - Dresden Unit 3 ML17252A5401974-06-11011 June 1974 Letter Confirming a 06/11/1974 Conversation Concerning a Small Leak in Line 3-3037B - Dresden Unit 3 ML17252B0321974-06-10010 June 1974 Letter Confirming a 06/10/1974 Conversation Concerning a Failure of a Three Quarter Inch Nipple on Reactor Feed Pump Dispatch Line 3-3201-24 - Dresden Unit 3 2017-09-09
[Table view] Category:Verbal Comm
MONTHYEARML17252B4162017-09-0909 September 2017 Letter Confirming a Conversation Concerning the Report of an Empty Spent Fuel Shipping Cask Which Had Some Areas of Removable Surface Contamination ML17252B4142017-09-0909 September 2017 Letter Confirming a Conversation Concerning the Failure of HPCI Valve Mo 2-2301-8 During a Maintenance Outage and the Discovery of a Broken Stem ML0528500652005-10-24024 October 2005 Minutes of Conference Call Regarding Dresden MSSV Setpoint Tolerance (Response to License Condition 4 from July 30, 2004 Amendment) ML0331002702002-08-19019 August 2002 Note to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331002432002-08-0707 August 2002 Note to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331001982002-05-0808 May 2002 Noie to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331001842002-05-0707 May 2002 Note to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331001972002-05-0707 May 2002 Note to Telephone Conversation - Robert O'Connell - NMSS-2002-A-0002 ML0331001732002-04-25025 April 2002 Note to Telephone Conversation - Robert O'Connell - NMSS 2002-A-0002 ML17252B4171976-12-0606 December 1976 Letter Confirming a 12/06/1976 Conversation Concerning the Receipt of an Empty Spent Fuel Shipping Cask Which Had Some Areas of Removeable Surface Contamination ML17252B4181976-12-0303 December 1976 Letter Confirming a Conversation Concerning Information Received That Indicates the R.W.M. Should Remain in Service or a Qualified Person Must Verify All Control Rod Movement Through 20% Power ML17252B4191976-12-0202 December 1976 Letter Confirming a 12/02/1976 Conversation Concerning Receipt of an Empty Spent Fuel Shipping Cask from GE Morris Operation Which Had Some Areas of Removable Surface Contamination ML17252B4571975-11-17017 November 1975 Letter Confirming a Conversation Concerning Quarterly Closure Timing of IC Main Steam Isolation Valve in Which the Closure Time Was Found at 2.7 Seconds ML17252B4581975-11-0404 November 1975 Letter Confirming a Conversation Concerning Discovery of High Level in the Torus While Running a HPCI Surveillance Check ML17252A4461975-07-31031 July 1975 Incident Notification Concerning Location of Broken Tack Welds on Jet Pump Restrainer Clamp Bolt Keepers During Tv Camera Examination of Unit 3 Jet Pumps - Dresden Unit 3 ML17252A9121975-04-25025 April 1975 Letter Confirming a 04/25/1975 Conversation Concerning Excessive Leakage Through Torus to Drywell Vacuum Breaker 3-1601-32B During Refuel Outage Local Leak Testing - Dresden Unit 3 ML17252A9131975-04-23023 April 1975 Letter Confirming a 04/23/1975 Conversation Concerning Failure of Feedwater Check Valves, 3-220-58A and 62A, and 3A Feedwater Line to Pass Local Leak Rate Test During Refuel Outage Surveillance - Dresden Unit 3 ML17252A7871975-03-19019 March 1975 Note to Confirm a Conversation Concerning Routine Main Steamline High Radiation Monitor Surveillance in Which the a and B Monitors Were Found to Have Set Points in Excess of Technical Specification Values - Dresden Unit 3 ML17252A7891975-03-19019 March 1975 Note to Confirm a Conversation Concerning Routine Main Steamline High Radiation Monitor Surveillance in Which the a and B Monitors Were Found to Have Set Points Exceeding the Techspec Value of 3 Times Background - Dresden Unit 3 ML17252A8241975-02-18018 February 1975 Note to Confirm a Conversation Concerning Discovery of a Leaking Containment Inerting Isolation Valve A03-1601-21 During Local Leak Rate Testing - Dresden Unit 3 ML17252A8251975-02-18018 February 1975 Note Confirming a Conversation Concerning Failure of Bergen Patterson Piping Restraint Number 19 on the Unit 3 HPCI Main Steam Line in the Dry-Well - Dresden Unit 3 ML17252B0291975-02-10010 February 1975 Letter Confirming a 02/10/1975 Conversation Concerning a Leak in a 3/4 Inch Vent Line at Weld on 3C Reactor Feed Pump Casing - Dresden Unit 3 ML17252A8231975-02-10010 February 1975 Note to Confirm a Conversation Concerning a Leak in a 3/4 Inch Vent Line at a Well on 3C Reactor Feed Pump Casing - Dresden Unit 3 ML17252A8371975-01-0707 January 1975 Note Confirming a Conversation Concerning a Xenon Transient Experienced on Unit 3 During a Control Rod Pattern Alteration - Dresden Unit 3 ML17252B0281975-01-0606 January 1975 Letter Confirming a 01/06/1975 Conversation Concerning Excess Chloride Content in Reactor Coolant Water During an Extended Reactor Cleanup System Maintenance Outage - Dresden Unit 3 ML17252A8321975-01-0606 January 1975 Note to Confirm a Conversation Concerning Excess Chloride Content in Unit 3 Reactor Coolant Water During a Extended Reactor Cleanup System Maintenance Outage - Dresden Unit 3 ML17252A4841974-12-0606 December 1974 Letter Confirming a 12/02/1974 Conversation Concerning the Discovery of Minor Leaks on the Minimum Flow Lines for 3A and 3B Reactor Feed Pumps - Dresden Unit 3 ML17252A4911974-10-23023 October 1974 Letter Confirming a 08/28/1974 Conversation Concerning a Failure to Maintain the 3A Core Spray Discharge Header in a Filled Condition - Dresden Unit 3 ML17252A4951974-10-0404 October 1974 Letter Confirming a 10/04/1974 Conversation Concerning the Discovery of DPI83-2352 with a Setpoint Greater than the Technical Specification ML17252A4971974-09-30030 September 1974 Letter Confirming a 09/30/1974 Conversation Concerning Discovery of Lits 3-263-72A and the Set Points Exceeding Technical Specifications ML17252A5001974-09-24024 September 1974 Letter Confirming a 09/24/1974 Conversation Concerning a Through Wall Crack Discovered on Torus Purge Inlet Line 3-8506-18 - Dresden Unit 3 ML17252A5011974-09-24024 September 1974 Letter Confirming a 09/21/1974 Conversation Concerning a Minor Leak from Feed Water Pressure Tap 3241-12A - Dresden Unit 3 ML17252A5051974-09-0909 September 1974 Letter Confirming a 09/09/1974 Conversation Concerning Failure of E Tip Valve to Close - Dresden Unit 3 ML17252B0311974-08-28028 August 1974 Letter Confirming a 08/23/1974 Conversation Concerning a Failure to Maintain the 3A Core Spray Discharge Header in a Filled Condition as Required by Technical Specifications - Dresden Unit 3 ML17252A5071974-08-14014 August 1974 Letter Confirming a 08/08/1974 Conversation Concerning a Failure of the Solenoid Operated Isolation Valve Associated with the 3B Traversing Encore Probe to Close - Dresden Unit 3 ML17252A5081974-08-0606 August 1974 Letter Confirming a 07/26/1974 Conversation Concerning Failure of the Seat Material of the Air Operated Primary Containment Isolation Valve A03-1601-22 - Dresden Unit 3 ML17252A5111974-07-29029 July 1974 Letter Confirming a 07/29/1974 Conversation Concerning Failure of the Seat Material of Air Operated Isolation Valve AO-3-1601-21 - Dresden Unit 3 ML17252A5121974-07-29029 July 1974 Letter Confirming a 07/26/1974 Conversation Concerning the Failure of the Seat Material of Air Operated Primary Containment Valve A03-1601-22 - Dresden Unit 3 ML17252A5151974-07-23023 July 1974 Letter Confirming a 07/19/1974 Conversation Concerning the Discovery of HPCI High Steam Flow Isolation Switch DPIS 3-2352 to Be Out of Flex - Dresden Unit 3 ML17252A5161974-07-19019 July 1974 Letter Confirming a 07/19/1974 Conversation Concerning Discovery of HPCI High Steam Flow Isolation Switch DPIS 3-2352 to Be Out of Flex - Dresden Unit 3 ML17252A5171974-07-16016 July 1974 Letter Confirming a 07/16/1974 Conversation Concerning the Failure to Reach the Required Containment Oxygen Concentration of 4 Percent within 24 Hours of Placing Mode Switch in Run Position - Dresden Unit 3 ML17252A5271974-07-0505 July 1974 Letter Confirming a 05/24/1974 Conversation Concerning the Discovery of a Set Point Drift of L.I.T.S. 3-263-72A Beyond the Technical Specification - Dresden Unit 3 ML17252A5261974-06-24024 June 1974 Letter Confirming a 06/24/1974 Conversation Concerning a Failure of the Air Supply to the Feed Water Regulating Valve on 06/23/1974 - Dresden Unit 3 ML17252A5291974-06-24024 June 1974 Letter Confirming a 06/24/1974 Conversation Concerning a Failure of the Air Supply to the Feed Water Regulating Valve on 06/23/1974 - Dresden Unit 3 ML17252A5251974-06-17017 June 1974 Letter Confirming a 06/17/1974 Conversation Concerning the Failure of Main Steam Drain Valve M03-220-2 to Operate Properly on 05/22/1974 - Dresden Unit 3 ML17252A5361974-06-17017 June 1974 Letter Confirming a 06/17/1974 Conversation Concerning a Failure of Main Steam Valve M03-220-2 to Operate on 05/22/1974 - Dresden Unit 3 ML17252A5241974-06-12012 June 1974 Letter Confirming a 06/12/1974 Conversation Concerning the Discovery of 2 Reactor High Pressure Scram Switches (PS-3-263-55A and C) with Set Points Above the Technical Specification Limit - Dresden Unit 3 ML17252A5231974-06-11011 June 1974 Letter Confirming a 06/11/1974 Conversation Concerning a Small Leak in Line 3-3037B - Dresden Unit 3 ML17252A5401974-06-11011 June 1974 Letter Confirming a 06/11/1974 Conversation Concerning a Small Leak in Line 3-3037B - Dresden Unit 3 ML17252B0321974-06-10010 June 1974 Letter Confirming a 06/10/1974 Conversation Concerning a Failure of a Three Quarter Inch Nipple on Reactor Feed Pump Dispatch Line 3-3201-24 - Dresden Unit 3 2017-09-09
[Table view] |
Text
50-249 Commonwealth_ Edison Company ONE FIRST NATIONAL PLAZA* CHICAGO. ILLINOIS Address Reply to' POST OFFICE BOX 767 *CHICAGO, ILLINOIS 60690 Dresden Nuclear Power station R. R. #1 Morris, Illinois 60450 WPW Ltr. #308-73 April 17, 197.3 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensiiig*
U. S. Atomic Ehergy Commission Washington, D.c. 20545 _
SUBJEX::T: UCENSE DPR . 25, DRESDEN NUCLEAR POWER STATION, UNIT #3, SFCTION 6.6.B.3 OF.THE TEX::HNICAL SPECIFICATIONS.
Dear Mr. Giambusso:
This is to report a condition:-relating to the operation or the Unit in which on April 9, 1973, a main steam line pressure switch setting was found to have drifted. Pressure switch PSL-3-261-.30A was found tripping at 816 PSI which
.is below the Technical Specification limit of' 850 PSI as described in Section
.3.2.a.
PROBLEM AND INVESTIGATION During a slirveillance inspection of* t_he -main steam line low pressure switches the set poi.iit for Barksdale switch 3-261-.30A was found to have drifted
- to 816 PSI~ The switch had been previously set at 871 PSI. The purpose of the pressure switch is to sense a drop in pressure due to a break in a ins.in steam line, and initiate a group I isolation. The electrical arrangement for a group I isolation initiation from a main steam line break is a one-out-of-two-twice logic. Therefore, it would have required two switch failures to prevent an isolation at 850 PSI.
../
Had a maiD steam line break occurred While the pressure setting of the PSL-3-261-JOA switch was 816 PSI all the main steam isolation valves would have closed at 850 PSI. Thus, the failure of switch .3-261-.30A did not present a hazard to.the public safety since an isolation would have occurred at 850 PSI as designed.
2602
CORRECTIVE ACTION The immediate corrective action was to reset the pressure switch setting to 872 PSI. The PSL-3-261-JOA swit~h will be replaced prior to the*
unit-startup due to its failure history {Reference our letter dated December 29, 1972).
- In addition, this switch type is presently under investigation by the manufacturer and the Station Instrument Department to determine the cause of set point drift. Fd;nciings of the investigation will dictate future corrective actions.
- f-"*
Sincerely,
~~- JJ(,(~ ,. -
/) ""' W. .P. Worden
.fW '< Superintendent
~
. '11' * ** : -
~'
~.
.'. ~- "" '" . ' :.....
-* '::. ~
cc: _WPtl ttr~* F~le
\
,-