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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20027A3321978-10-27027 October 1978
RO#77-054/03X-1 on 771102:CRD H-5 Uncoupled During Functional Testing Caused by Unlatched Inner Filter & Abnormally Long Uncoupling Rod.Inner Filter Pull Test in Reassembly Procedure & Improved QA Coverage Incorporated
ML19352A1171974-12-16016 December 1974
Ro:On 741213,during Refueling Outage Circumferential Cracks Found in Unit 2 Stainless Steel Loop B Bypass Line.Cause Not Stated.Corrective Action Being Reviewed
ML20003C3781974-05-27027 May 1974
Ro:On 740527,diesel Generator 2/3 Declared Inoperable Due to Unstable Load & Machine Inability to Carry Full Load. Cause Not Stated.Required Surveillance & Investigation Initiated
ML19352A1191972-09-29029 September 1972
Ro:On 720919,during Routine Calibr of Reactor Low Pressure Permissive Switches,Two Setpoints Drifted Above Tech Specs Value of 350 Psig.Switches Reset & Will Be Sent to Ctr of Trip Setting Span in Future
1978-10-27
[Table view]
Category:LER)
MONTHYEARML20027A3321978-10-27027 October 1978
RO#77-054/03X-1 on 771102:CRD H-5 Uncoupled During Functional Testing Caused by Unlatched Inner Filter & Abnormally Long Uncoupling Rod.Inner Filter Pull Test in Reassembly Procedure & Improved QA Coverage Incorporated
ML19352A1171974-12-16016 December 1974
Ro:On 741213,during Refueling Outage Circumferential Cracks Found in Unit 2 Stainless Steel Loop B Bypass Line.Cause Not Stated.Corrective Action Being Reviewed
ML20003C3781974-05-27027 May 1974
Ro:On 740527,diesel Generator 2/3 Declared Inoperable Due to Unstable Load & Machine Inability to Carry Full Load. Cause Not Stated.Required Surveillance & Investigation Initiated
ML19352A1191972-09-29029 September 1972
Ro:On 720919,during Routine Calibr of Reactor Low Pressure Permissive Switches,Two Setpoints Drifted Above Tech Specs Value of 350 Psig.Switches Reset & Will Be Sent to Ctr of Trip Setting Span in Future
1978-10-27
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20249C8491999-09-30030 September 1999
1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with
ML20217A1691999-09-22022 September 1999
Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers
ML20210R6081999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With
ML20209E1291999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20209J3481999-06-30030 June 1999
1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With
ML20210D3071999-06-30030 June 1999
Corrected Page 8 to MOR for June 1999 for DNPS Unit 3
ML20195G6381999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20195B2591999-05-19019 May 1999
Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations
ML20206N2821999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20206B1901999-03-31031 March 1999
First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with
ML20205N7491999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20207M6921999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20207E9311999-02-26026 February 1999
Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced
ML20199M0891999-01-22022 January 1999
Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc
ML20199D3261998-12-31031 December 1998
10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With
ML20199C8951998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3
ML20205M7061998-12-31031 December 1998
Unicom Corp 1998 Summary Annual Rept. with
ML20197G8591998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With
ML20196A4191998-11-19019 November 1998
Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB
ML20196J0061998-11-19019 November 1998
Rev 66 to Topical Rept CE-1-A, QA Program
ML20195D2861998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With
ML20154L3681998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20154N4131998-09-30030 September 1998
1998 Third Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments
ML20153C5061998-09-21021 September 1998
SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station,Unit 1
ML20151Y2711998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20237E2331998-08-21021 August 1998
Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept
ML20237A7161998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20236Q5851998-06-30030 June 1998
1998 Second Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments
ML20236F8131998-06-30030 June 1998
Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co
ML20236T8331998-06-30030 June 1998
COLR for Dresden Station Unit 3,Cycle 15
ML20236T8391998-06-30030 June 1998
Rev 1 to EMF-96-141, Dresden Unit 3 Cycle 15 Reload Analysis Rept
ML20236M6041998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20248M3021998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20248F3531998-05-21021 May 1998
Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted
ML20247F3391998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20217D0281998-04-22022 April 1998
Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies
ML20216D4411998-03-31031 March 1998
First Quarter Rept of Completed Changes,Tests & Experiments for 10CFR5059
ML20216C9651998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20216E2531998-02-28028 February 1998
Monthly Operating Repts for Feb 1998 for Dresden Nuclear Power Station
ML20202F7831998-01-31031 January 1998
Monthly Operating Repts for Jan 1998 for Dresden Nuclear Power Station
ML20199K1651998-01-23023 January 1998
Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr
ML20198P5321997-12-31031 December 1997
Monthly Operating Repts for Dec 1997 for Dresden Nuclear Power Station
ML20198P7021997-12-31031 December 1997
Fourth Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59
ML20216D3611997-12-31031 December 1997
Unicom Corp 1997 Summary Annual Rept
ML20203F8781997-11-30030 November 1997
Monthly Operating Repts for Nov 1997 for Dresden Nuclear Power Station
ML20199B0701997-10-31031 October 1997
Monthly Operating Repts for Oct 1997 for Dresden Nuclear Power Station
ML20217H7201997-09-30030 September 1997
Monthly Operating Repts for Sept 1997 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20210V2401997-09-19019 September 1997
Rev 65g to Topical Rept CE-1-A, Comm Ed QA Manual
ML20216J3781997-08-31031 August 1997
Monthly Operating Repts for Aug 1997 for DNPS
ML20210H5511997-07-31031 July 1997
Monthly Operating Repts for July 1997 for DNPS IAW RG 1.16 & GL 97-02
1999-09-30
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Text
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.u Commonweahh Edison Company
,i p ,g 72 WEST ADAMS S T ft E E T
- C H I C A G O. ILLINOIS 7 L g,N m a.s, roST otrict sox 747
- c n Ic A c o, I L L IN o IS 40 4 9 0 007c M, Dresden Nuclear Power Station q or s Illinois 60450 h Nif // September 29, 1972 r ,\
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t 00T3 ;97.- G-s..!. HAc g,; ~
Mr. A. Giambusso {W. .; s Deputy Director for Reactor Projects vy g{ /
//
Directorate of Licensing , ,s U. S. Atomic Energy Coc: mission 1,t ( 6 Washington, D. C. 20545
SUBJECT:
LICENSE DPR-19, DRESDEN NUCLEAR POWER STATION, UNIT #2, SECTION 6.6.B.3 0F THE TECHNICAL SPECIFICATIONS.
Dear Mr. Giambusso:
This is to report a condition relating to the operation of the unit in which, on September 19, 1972, the setpoints of two of the reactor low pressure permis::ive switches (for opening core spray and low pressure coolant injection admission valves) drif ted beyond the values established in Table 3.2.2 of the Technical Specifications.
PROBLEM AND INVESTIGATQ ,
l On September 19, 1972, during routine calibration of the reactor low pressure permissive switches (required every three months by Technical l Specifications), two of the switches setpoints were found to have drif ted l above the Technical Specifications value of 350 psig.
l l The subject switches, PS-2-263-52A1 and FIS-2-263-52B2, were found set at 357 psig and 352 psig respectively. PS-2-263-51A1 is a Heletron switch, model number 372-6SS-49A-292 with a range of 28-1400 psig and an accuracy of + 17.. PIS-2-263-52B2 is an ITT Barton Switch, serial number 288-5560, with a range of 0-500 psig and an accuracy of + 0.2%.
l CORRECTIVE ACTION At the time of calibration, PS-2-263-52A1, and PIS-2-263-52B2 were l reset to 345 psig and 346 psig reactor pressure respectively.
saas l
M.
PJb3lloO3G
Mr. A. Giambusos Srptember 29, 1972 J
These switches do not have a history of drifting. They have pre-viously been set as close to 350 psig as practical. Since these switches have a 50 psig permissive trip setting span (Table 3.2.2 of the Technical Specifications) they will be set to the center of this span to prevent future recurrences.
Sincerely, bb b Nsb W. P. Worden Superintendent Dresden Nuclear Power Ststion WFW:do f
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