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| | number = ML17252A789 | | | number = ML17252A789 |
| | issue date = 03/19/1975 | | | issue date = 03/19/1975 |
| | title = 03/19/1975 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 | | | title = 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 |
| | author name = Stephenson B B | | | author name = Stephenson B |
| | author affiliation = Commonwealth Edison Co | | | author affiliation = Commonwealth Edison Co |
| | addressee name = Keppler J G | | | addressee name = Keppler J |
| | addressee affiliation = NRC/NRR | | | addressee affiliation = NRC/NRR |
| | docket = 05000249 | | | docket = 05000249 |
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| =Text= | | =Text= |
| {{#Wiki_filter:A. B. UNITED STATES ATOMIC ENERGY COMMISSION DIRECTORATE OF REGULATORY OPERATIONS REGION Ill 799 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 60137 RO Inspection Report Transmittal Date | | {{#Wiki_filter:UNITED STATES ATOMIC ENERGY COMMISSION DIRECTORATE OF REGULATORY OPERATIONS REGION Ill 799 ROOSEVELT ROAD TELEPHONE GLEN ELLYN, ILLINOIS 60137 (312.) 858-2860 A. RO Inspection Report No. |
| * Distribution: | | Transmittal Date |
| RO Chief, FS&EB RO:HQ (5) DR Central Files Regulatory Standards Licensing (13) RO Files RO Inquiry Report No. Transmittal Date Distribution: | | * Distribution: Distribution: |
| RO Chief, FS&EB RO:HQ (5) DR Central Files Regulatory Standards Licensing (13) RO Files No. (3) (3) Distribution: | | RO Chief, FS&EB RO Chief, FS&EB RO:HQ (5) RO:HQ (4) |
| RO Chief, FS&EB RO:HQ (4) L:D/D for Fuels DR Central Files RO Files Distribution: | | DR Central Files L:D/D for Fuels & Materials Regulatory Standards (3) DR Central Files Licensing (13) RO Files RO Files B. RO Inquiry Report No. |
| RO Chief, FS&EB
| | Transmittal Date Distribution: Distribution: |
| * RO:HQ DR Central Files RO Files TELEPHONE (312.) 858-2860
| | RO Chief, FS&EB RO Chief, FS&EB |
| & Materials C. Incident Notification From:Commonwealth Edison -Dresden Unit 3 (Licensee
| | * RO:HQ (5) RO:HQ DR Central Files DR Central Files Regulatory Standards (3) RO Files Licensing (13) |
| & Docket No. (or License No.) 50-249 Transmittal Date Distribution: | | RO Files C. Incident Notification From:Commonwealth Edison - Dresden Station~ Unit 3 (Licensee & Docket No. (or License No.) 50-249 Transmittal Date April 2, 1975 Distribution: Distribution: |
| RO Chief, FS&EB RO:HQ (4) Licensing (4) DR Central Files RO Files April 2, 1975 Distribution: | | RO Chief, FS&EB RO Chief, FS&EB RO:HQ (4) RO:HQ (4) |
| RO Chief, FS&EB RO:HQ (4) L:D/D for Fuels & Materials DR Central Files RO Files /J4; f
| | Licensing (4) L:D/D for Fuels & Materials DR Central Files DR Central Files RO Files RO Files |
| | /J4; f |
|
| |
|
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| '* . 0 799 ROOSEVELT.
| | 799 ROOSEVELT. RD . .. . *_ ' ..*. '. .(' t)-:>8" I .* * .. E;.* ~- . ~ r-l. *~ 1,-* |
| RD . . . . *_ ' .. *. '. . (' t)-:>8" I .* * .. E;.* . r-l. 1,-* GLEN ELLYN IL. 6.0i3*7:. | | GLEN ELLYN IL. 6.0i3*7:. . ' * ..c ~.r;,; i~' ~ (' ...) 1::-" : |
| . ' * ..c (' ... ) 1::-" : | | ~ -DRESDEN ;~\. *:- .* . *~i *t ~ ~: ~ ;(' |
| | 1 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| . | | . DPR.;25 NUCLEAR _POWER. ;TAT iON, UNIT! |
| DPR.;25 -DRESDEN NUCLEAR _POWER. ;TAT1iON, UNIT! | | '* . . , . . . . . . . . I:- c.J. : .. |
| *:-.* . *t ;(' . , . . . . . . . . I:-c.J. : .. THIS WILL -CONFIRM A *coNVERSATION WITH P JOHNSON YOUR E* ! 10: 15 HOURS THIS DATE. CONCERNING ROUTINE MAIN. STEAMLINE | | THIS WILL -CONFIRM A *coNVERSATION WITH P JOHNSON o~. YOUR OFFiqf~~I~ ~ E* |
| ( RADIATION rwioNrToR sERvEiLLANcE*
| | '-*~ *~ |
| *AND *s*. | | 10: 15 HOURS THIS DATE. CONCERNING ROUTINE MAIN. STEAMLINE HIGH.,~::: ( |
| .** c *** -* .: *, ' ** * * .. --: * ... | | ~ RADIATION rwioNrToR sERvEiLLANcE* .i~LwHicH rH.E;~A~ *AND *s*. MONIToRs:.".~--*-.,;~*.,:'._ .** |
| .... | | ~- )~,. ~.'":',~:*, ,-~*~""': -~._.**~~ *-:.-.:.~::...:.*'"f*J:~~:' **:-* ~.~.... :f:**~-*"';->**:. . , ._ *. . . ':.* , ~ . . -:-.(~~*-*~"'.">- . |
| ... | | c c *** - * .: *, ' ** * * .. - -: * ... .... ... ** :_- ....... : * . " ' . -. |
| ** | | 0 .WERE FOUND TO.:~~ v~_*. SET. PO IN~S. l~,-.'~~-~.~~~~;~/-9.~i-X,~~~*~s. w.~~~H, CO~RESPON~ ~:~:'.t-:*~~ |
| :_-....... :*."'. -. | | TO THE TECHSPEC *VALUE OF' "3 TIMES -BACKGROUND".'*~- -THE. MONITORS,. WERE* .... *,'*':"t! |
| **:-* .... | | *. '* . . ',.***.*;:;.'., .... *.>;.~:,*-~,-::.-::.--: .. :** ..* . .**::.- ~** *-.'~~-- .*. |
| . ,,._ *. . . ':.* , .... | | IMMEDIA.TELY. RESET TO REQUIR~D* SET. P,~INT~.*- ~LL''OTHER:*MONIT9RS. WERE .:*:.* , . . ( |
| . . WERE FOUND SET. PO c TO THE TECHSPEC
| | OPERATIONAL AT THE TIME. ** * |
| *VALUE OF' "3 TIMES | | <* -* * -~ *' * * : |
| -THE. MONITORS,. | | * _ .... *." |
| WERE* .... *,'*':"t! | | : l .~ - .';. . ,_ . . . . -':**: ~'- ~ /,,* *.: . . . .. . |
| *. '* . . ',.***.*;:;.'., | | 0 .._ |
| .... | | 6 1201 |
| .. :** .. * .. **::.- | | <~ B STEPHENSON. SUPERIN1.ENDENT .. DRESDEN* NUCLEAR_ POWE~ .S~AT ION |
| .*. IMMEDIA.TELY. | | * J * * * :., * : * * : ** ~~I,*:*,'~.'.":*,-*,*~*.* * * *, ', ',*' *, ~ *: - * .*. * ~.:*_," * *.:. .~ I |
| RESET TO SET. | | '*' COMMONWEAL;~. E . . ~"i~oN c"o :R'R *:~*~OR*~i~"'~l. *~~;6:'~*-:c:*:*:,~"""'::;~ -;::-~~-<~"":i+--a-*.<"""o*;:"""~----"""'.'.._....,_,.,,..,&.- . ...._ |
| WERE .:*:.* , . . ( OPERATIONAL AT THE TIME. **: .'. * ,*, *, . ._,. ' . * * : . .-,. ** * . * *** <* -* * *' ** :*_ .... *." : l . -.'; . ..,_ . . . . -':**: /,,* *.: . . . .. . 0 6.._1201 B STEPHENSON. | | ~- . .. |
| SUPERIN1.ENDENT | | - .. . ; .. :.. ; _'. ** ~.'_:r,.':~: ~- * . . , .* **.i.i*'. . . |
| .. DRESDEN* | | NNNN |
| NUCLEAR_ | | ~ *. n ... |
| ION | | . ** j |
| * J * * * :., * : * * : ** | | ) .. . t . |
| * * *, ', ',*' *, *: -* .*. * | | MAR 2. 1 1975 SF-1201 (RS-89) |
| * *.:. I '*' *. | | ---c}} |
| E ... | |
| c"o :R'R | |
| .. .... _ ....
| |
| ...... -:*&-... """' .. *'"""* ''-* . . . NNNN ) .. . t . MAR 2. 1 1975 SF-1201 (RS-89) -. . . ; .. : .. ; _ '. ** * . . , .* **.i.i*'. . . .. .. . . '* ... * . . *
| |
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|
|---|
Category:Licensee Event Report (LER)
MONTHYEARML20135G7442020-05-14014 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
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
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
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
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
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
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
ML17252B1961980-04-29029 April 1980
LER 80-017/03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start
2020-05-14
[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
UNITED STATES ATOMIC ENERGY COMMISSION DIRECTORATE OF REGULATORY OPERATIONS REGION Ill 799 ROOSEVELT ROAD TELEPHONE GLEN ELLYN, ILLINOIS 60137 (312.) 858-2860 A. RO Inspection Report No.
Transmittal Date
- Distribution: Distribution:
RO Chief, FS&EB RO Chief, FS&EB RO:HQ (5) RO:HQ (4)
DR Central Files L:D/D for Fuels & Materials Regulatory Standards (3) DR Central Files Licensing (13) RO Files RO Files B. RO Inquiry Report No.
Transmittal Date Distribution: Distribution:
RO Chief, FS&EB RO Chief, FS&EB
- RO:HQ (5) RO:HQ DR Central Files DR Central Files Regulatory Standards (3) RO Files Licensing (13)
RO Files C. Incident Notification From:Commonwealth Edison - Dresden Station~ Unit 3 (Licensee & Docket No. (or License No.) 50-249 Transmittal Date April 2, 1975 Distribution: Distribution:
RO Chief, FS&EB RO Chief, FS&EB RO:HQ (4) RO:HQ (4)
Licensing (4) L:D/D for Fuels & Materials DR Central Files DR Central Files RO Files RO Files
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799 ROOSEVELT. RD . .. . *_ ' ..*. '. .(' t)-:>8" I .* * .. E;.* ~- . ~ r-l. *~ 1,-*
GLEN ELLYN IL. 6.0i3*7:. . ' * ..c ~.r;,; i~' ~ (' ...) 1::-" :
~ -DRESDEN ;~\. *:- .* . *~i *t ~ ~: ~ ;('
1
SUBJECT:
. DPR.;25 NUCLEAR _POWER. ;TAT iON, UNIT!
'* . . , . . . . . . . . I:- c.J. : ..
THIS WILL -CONFIRM A *coNVERSATION WITH P JOHNSON o~. YOUR OFFiqf~~I~ ~ E*
'-*~ *~
10: 15 HOURS THIS DATE. CONCERNING ROUTINE MAIN. STEAMLINE HIGH.,~::: (
~ RADIATION rwioNrToR sERvEiLLANcE* .i~LwHicH rH.E;~A~ *AND *s*. MONIToRs:.".~--*-.,;~*.,:'._ .**
~- )~,. ~.'":',~:*, ,-~*~""': -~._.**~~ *-:.-.:.~::...:.*'"f*J:~~:' **:-* ~.~.... :f:**~-*"';->**:. . , ._ *. . . ':.* , ~ . . -:-.(~~*-*~"'.">- .
c c *** - * .: *, ' ** * * .. - -: * ... .... ... ** :_- ....... : * . " ' . -.
0 .WERE FOUND TO.:~~ v~_*. SET. PO IN~S. l~,-.'~~-~.~~~~;~/-9.~i-X,~~~*~s. w.~~~H, CO~RESPON~ ~:~:'.t-:*~~
TO THE TECHSPEC *VALUE OF' "3 TIMES -BACKGROUND".'*~- -THE. MONITORS,. WERE* .... *,'*':"t!
- . '* . . ',.***.*;:;.'., .... *.>;.~:,*-~,-::.-::.--: .. :** ..* . .**::.- ~** *-.'~~-- .*.
IMMEDIA.TELY. RESET TO REQUIR~D* SET. P,~INT~.*- ~LLOTHER:*MONIT9RS. WERE .:*:.* , . . (
OPERATIONAL AT THE TIME. ** *
<* -* * -~ *' * * :
- l .~ - .';. . ,_ . . . . -':**: ~'- ~ /,,* *.: . . . .. .
0 .._
6 1201
<~ B STEPHENSON. SUPERIN1.ENDENT .. DRESDEN* NUCLEAR_ POWE~ .S~AT ION
- J * * * :., * : * * : ** ~~I,*:*,'~.'.":*,-*,*~*.* * * *, ', ',*' *, ~ *: - * .*. * ~.:*_," * *.:. .~ I
'*' COMMONWEAL;~. E . . ~"i~oN c"o :R'R *:~*~OR*~i~"'~l. *~~;6:'~*-:c:*:*:,~"""'::;~ -;::-~~-<~"":i+--a-*.<"""o*;:"""~----"""'.'.._....,_,.,,..,&.- . ...._
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- .. . ; .. :.. ; _'. ** ~.'_:r,.':~: ~- * . . , .* **.i.i*'. . .
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MAR 2. 1 1975 SF-1201 (RS-89)
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