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| | issue date = 10/05/1972 | | | issue date = 10/05/1972 |
| | title = Letter Confirming a 10/05/1972 Conversation Concerning the Discovery of ECCS 350 PSI Low Reactor Pressure Switches to Be Out of Calibration - Dresden Unit 3 | | | title = Letter Confirming a 10/05/1972 Conversation Concerning the Discovery of ECCS 350 PSI Low Reactor Pressure Switches to Be Out of Calibration - Dresden Unit 3 |
| | author name = Worden W P | | | author name = Worden W |
| | author affiliation = Commonwealth Edison Co | | | author affiliation = Commonwealth Edison Co |
| | addressee name = Grier B | | | addressee name = Grier B |
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| =Text= | | =Text= |
| {{#Wiki_filter:. . .... . -**: '* -** ... ,., ..... *,.,, .* ... . ,*, ... , ,,__;* ..... *.: .. -: .... , ... ' '*. . ' ' . ..J <!)1)' Py'-{ 7 \ l 444A EST OCT 6 72 DEA544 DE DEG 145C1845)C1-03 255 2C PD 10/05/7 2 184 0 ICS IPMVEIF MVN 0 r.x:l*-H I 1 ZCZC 193 F AM PDB TDVE MORRIS ILL 5 335P CDT. >t t; , r:rl I 1'.:4.-..,_ l PMS BOYCE GREAR DIR DIV OF DLR DONT FONE REGION 3 US .. ROOSEVELT RD GLEN ELLYN ILL 60137 Z -\ w C> o; : \ E-1 § o:>''O i SUBJECT DPR2 DRESDEN NUCLEAR POWER STATION UNIT 3o < l THIS WILL CONFIRM A CONVERSATION WITH MR H* DANCE OF YOUR fil ! OFFICE AT 1400 HOURS THIS DATE CONCERNING ECCS 350 PSI eg ] l Low REACTOR PRESSURE SWITCHES BEING OUT or CALIBRATION £::!]: \ THAT TtvO OF THE FOUR SWITCHES HAD TRIPPE.D SETTING GREATER .; C!)H \ THE LIMIT IN TABLE 3 0 2o 2. OF TECHNICAL SPECIFICATIONS. z I i::.1 0 Q) 0 \ TABLE 3o2o2o STATE THE TRIP SETTING SHOULD BE GREATER THAN E-1 E 330 ?SIG AND LESS THAN 350 PSIG PRESSURE SWITCH 3-253-52A2 '. .t *1 TRIP SETTING WAS FOUND TO BE 371 PSIGo PRESSURE SWITCH if i3 ,: < .. SF-1201 (RS-69) OCT l 0 1972 . Q. ... ' '*' 33-263-52B2 TRIP SETTING WAS FOUND TO BE 355 PSIG. PRIOR TO THIS CALIBRATION THE "AS LEFTw SETTING ON THESE SWITCHES WAS 355 PLUS OR MINUS 5 PS!Go OUR LIMIT FOR THESE SWITCHES HAS NOW BEEN CHANGED TO 325 PLUS OR MINUS 10 PSIGo THIS SETTING IS IN THE CENTER OF TECHNICAL SPECIFICATIONS PRESSURE RANGE AND ALLOWS GREATER MARGIN FOR INSTRUMENT DRIFT WALTER Po WORDEN7 SUPTo DRESDEN NUCLEAR POWER STATION DPR25 3 1400 ECCS 350 PSI 10-4-72 1500 3o2o2o 3o2o2 330 350 371 33-253-52B2 355 355 5 325 10 .0 " SF-1201 (R>eQ)}} | | {{#Wiki_filter:~egul(i,tory . |
| | .-._~,~-1 |
| | .....*,., .* ... . ,*,. ., , __;*. . . *.:..-:... ,. ****~. ' '*. . ' ' . ..J 444A EST OCT 6 72 DEA544 DE <!)1)' Py'-{ 7 -::~;>J~~ \ |
| | DEG 145C1845)C1-03 255 2C 27~) PD 10/05/7 2 ICS IPMVEIF MVN 184 0 |
| | **1,!.~t ~~~ l1 0 r.x:l*-H I ZCZC 193 F AM PDB TDVE MORRIS ILL 5 335P CDT. >t ~ t; ,l r:rl I 1'.:4.-..,_ |
| | Z ~ ~\'\*,'\o - \ |
| | PMS BOYCE GREAR DIR DIV OF COMPLIANCE~ DLR DONT FONE REGION 3 US A!Q.~_I.~_..-~!'JERG':.::COM~799 ROOSEVELT RD GLEN ELLYN ILL 60137 |
| | :::\~ ~~\~** ~ \ |
| | ~re:\-'<\ |
| | E-1 w |
| | § C> o; i |
| | l o:>''O SUBJECT DPR2 DRESDEN NUCLEAR POWER STATION UNIT 3o ~ ~< ,--~ |
| | THIS WILL CONFIRM A CONVERSATION WITH MR H* DANCE OF YOUR ~ fil ~ .~ ! |
| | OFFICE AT 1400 HOURS THIS DATE CONCERNING ECCS 350 PSI eg ~ ] l Low REACTOR PRESSURE SWITCHES BEING OUT or CALIBRATION SHOWE~ ~ £::!]: \ |
| | THAT TtvO OF THE FOUR SWITCHES HAD TRIPPE.D SETTING GREATER TH~~ ~~~.-1.; \ |
| | C!)H THE LIMIT IN TABLE 3 2o 2. OF TECHNICAL SPECIFICATIONS. |
| | 0 ~~z I r~ ~ |
| | TABLE 3o2o2o STATE THE TRIP SETTING SHOULD BE GREATER THAN E-1 ~ E~ .-~.:0 \ i::.1 0 Q) 330 ?SIG AND LESS THAN 350 PSIG PRESSURE SWITCH 3-253-52A2 ~ ~ ~ *~ '. .t *1 TRIP SETTING WAS FOUND TO BE 371 PSIGo PRESSURE SWITCH if i3 ,: <.. :*~ |
| | SF-1201 (RS-69) OCT l 0 1972 . ~ ~ Q. ... ' ~. '*' |
| | 33-263-52B2 TRIP SETTING WAS FOUND TO BE 355 PSIG. |
| | PRIOR TO THIS CALIBRATION THE "AS LEFTw SETTING ON THESE SWITCHES WAS 355 PLUS OR MINUS 5 PS!Go OUR LIMIT FOR THESE SWITCHES HAS NOW BEEN CHANGED TO 325 PLUS OR MINUS 10 PSIGo THIS SETTING IS IN THE CENTER OF TECHNICAL SPECIFICATIONS PRESSURE RANGE AND ALLOWS GREATER MARGIN FOR INSTRUMENT DRIFT WALTER Po WORDEN 7 SUPTo DRESDEN NUCLEAR POWER STATION DPR25 3 1400 ECCS 350 PSI 10-4-72 1500 3o2o2o 3o2o2 330 350 3-~3-52A2 371 33-253-52B2 355 355 5 325 10 .0 SF-1201 (R>eQ)}} |
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Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
[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
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l o:>O SUBJECT DPR2 DRESDEN NUCLEAR POWER STATION UNIT 3o ~ ~< ,--~
THIS WILL CONFIRM A CONVERSATION WITH MR H* DANCE OF YOUR ~ fil ~ .~ !
OFFICE AT 1400 HOURS THIS DATE CONCERNING ECCS 350 PSI eg ~ ] l Low REACTOR PRESSURE SWITCHES BEING OUT or CALIBRATION SHOWE~ ~ £::!]: \
THAT TtvO OF THE FOUR SWITCHES HAD TRIPPE.D SETTING GREATER TH~~ ~~~.-1.; \
C!)H THE LIMIT IN TABLE 3 2o 2. OF TECHNICAL SPECIFICATIONS.
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TABLE 3o2o2o STATE THE TRIP SETTING SHOULD BE GREATER THAN E-1 ~ E~ .-~.:0 \ i::.1 0 Q) 330 ?SIG AND LESS THAN 350 PSIG PRESSURE SWITCH 3-253-52A2 ~ ~ ~ *~ '. .t *1 TRIP SETTING WAS FOUND TO BE 371 PSIGo PRESSURE SWITCH if i3 ,: <.. :*~
SF-1201 (RS-69) OCT l 0 1972 . ~ ~ Q. ... ' ~. '*'
33-263-52B2 TRIP SETTING WAS FOUND TO BE 355 PSIG.
PRIOR TO THIS CALIBRATION THE "AS LEFTw SETTING ON THESE SWITCHES WAS 355 PLUS OR MINUS 5 PS!Go OUR LIMIT FOR THESE SWITCHES HAS NOW BEEN CHANGED TO 325 PLUS OR MINUS 10 PSIGo THIS SETTING IS IN THE CENTER OF TECHNICAL SPECIFICATIONS PRESSURE RANGE AND ALLOWS GREATER MARGIN FOR INSTRUMENT DRIFT WALTER Po WORDEN 7 SUPTo DRESDEN NUCLEAR POWER STATION DPR25 3 1400 ECCS 350 PSI 10-4-72 1500 3o2o2o 3o2o2 330 350 3-~3-52A2 371 33-253-52B2 355 355 5 325 10 .0 SF-1201 (R>eQ)}}