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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20028D2291983-01-0707 January 1983 Revised LER 81-045/03X-1:on 810730,after Unit Trip,Three Action Statements Entered.Auxiliary Feedwater Pump 1-2 Did Not Operate Properly.Shield Bldg Integrity Lost When Panel Blown Out.Main Steam Safety Valve Lifted at Low Setpoint ML20049A8471981-09-22022 September 1981 LER 80-091/01X-14:on 801223,required Analysis Indicated That 26 Walls Would Be Overstressed During Seismic Event & 11 Others Would Be Overstressed by Compartment Pressurization. Caused by Change in Analytical Methodology ML20004E4851981-06-0505 June 1981 LER 81-024/03X-1:on 810418,bus J Was Rapidly Taken Out of Svc Which Resulted in Loss of Decay Heat Pump 1-1.Caused by Personnel & Procedural Error.Procedure Mod Written ML19331B6591980-08-0808 August 1980 LER 80-055/03L-0:on 800709,position Indication for ECCS Room Ventilation Exhaust damper,HA5441,lost.Cause Unknown.Damper Manually Closed ML19329F9661980-07-0303 July 1980 LER 80-045/03L-0:on 800609,while Preparing to Perform ST 5091.01,NI-2 Found Partially Disconnected from Equipment in Control Room.Apparently Caused by Personnel Error.Info Tags Hung on Coax Cables to Insure Proper Connection ML19332A5601980-02-28028 February 1980 LER 80-012/03L-1:on 800201,reactor Operator Noticed Control Room Position Indication Was Lost for Letdown Cooler Isolation Valve MU2A.Caused by Const Personnel Bumping Into Disconnect Switch Breaker.Switch Repositioned ML19290C2351980-01-0505 January 1980 LER 79-127/03L-0:on 791210,IBM Sys 7 Contact Data Logger Failed Rendering Fire & Radiation Remote Monitoring Inoperable.Caused by Intermittent Equipment Problem of Unknown Origin.Computer Program Reloaded ML19270F3831979-01-31031 January 1979 LER 79-003/03L-0 on 790104:control Room Emergency Ventilation Sys Damper HV5311E Inoperable.Caused by Leaking Pneumatic Operator.New Operator Installed.Damper Operated & Tested for Response Time & Declared Operable ML20027A2401978-09-27027 September 1978 LER 78-067/03L-1:re Failure Data for Decay Heat Flow.Caused by Personnel Error in Deenergizing Essential Bus 1983-01-07
[Table view] Category:RO)
MONTHYEARML20028D2291983-01-0707 January 1983 Revised LER 81-045/03X-1:on 810730,after Unit Trip,Three Action Statements Entered.Auxiliary Feedwater Pump 1-2 Did Not Operate Properly.Shield Bldg Integrity Lost When Panel Blown Out.Main Steam Safety Valve Lifted at Low Setpoint ML20049A8471981-09-22022 September 1981 LER 80-091/01X-14:on 801223,required Analysis Indicated That 26 Walls Would Be Overstressed During Seismic Event & 11 Others Would Be Overstressed by Compartment Pressurization. Caused by Change in Analytical Methodology ML20004E4851981-06-0505 June 1981 LER 81-024/03X-1:on 810418,bus J Was Rapidly Taken Out of Svc Which Resulted in Loss of Decay Heat Pump 1-1.Caused by Personnel & Procedural Error.Procedure Mod Written ML19331B6591980-08-0808 August 1980 LER 80-055/03L-0:on 800709,position Indication for ECCS Room Ventilation Exhaust damper,HA5441,lost.Cause Unknown.Damper Manually Closed ML19329F9661980-07-0303 July 1980 LER 80-045/03L-0:on 800609,while Preparing to Perform ST 5091.01,NI-2 Found Partially Disconnected from Equipment in Control Room.Apparently Caused by Personnel Error.Info Tags Hung on Coax Cables to Insure Proper Connection ML19332A5601980-02-28028 February 1980 LER 80-012/03L-1:on 800201,reactor Operator Noticed Control Room Position Indication Was Lost for Letdown Cooler Isolation Valve MU2A.Caused by Const Personnel Bumping Into Disconnect Switch Breaker.Switch Repositioned ML19290C2351980-01-0505 January 1980 LER 79-127/03L-0:on 791210,IBM Sys 7 Contact Data Logger Failed Rendering Fire & Radiation Remote Monitoring Inoperable.Caused by Intermittent Equipment Problem of Unknown Origin.Computer Program Reloaded ML19270F3831979-01-31031 January 1979 LER 79-003/03L-0 on 790104:control Room Emergency Ventilation Sys Damper HV5311E Inoperable.Caused by Leaking Pneumatic Operator.New Operator Installed.Damper Operated & Tested for Response Time & Declared Operable ML20027A2401978-09-27027 September 1978 LER 78-067/03L-1:re Failure Data for Decay Heat Flow.Caused by Personnel Error in Deenergizing Essential Bus 1983-01-07
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & PNPP QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1998-011, :on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle1999-09-0303 September 1999
- on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle
ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1999-003, :on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With1999-08-26026 August 1999
- on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With
ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-013, :on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With1999-06-24024 June 1999
- on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With
ML20212H9961999-06-22022 June 1999 Safety Evaluation Supporting Amend 233 to License NPF-3 ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G6661999-06-0808 June 1999 Safety Evaluation Supporting Amend 232 to License NPF-3 ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20206U7371999-05-19019 May 1999 Safety Evaluation Supporting Amend 231 to License NPF-3 ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1999-002, :on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With1999-03-0505 March 1999
- on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With
ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206U2441999-02-0909 February 1999 Safety Evaluation Supporting Amend 229 to License NPF-3 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20198K7671998-12-21021 December 1998 Safety Evaluation Supporting Amend 228 to License NPF-3 ML20196J5641998-12-0101 December 1998 SE Concluding That Firstenergy Nuclear Operating Co Qualified to Hold License to Extent of & for Purposes Proposed by Application for Approval of Transfer of Operating Authority ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-012, :on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With1998-11-17017 November 1998
- on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With
05000346/LER-1998-011, :on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With1998-11-13013 November 1998
- on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With
05000346/LER-1998-009, :on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With1998-11-13013 November 1998
- on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With
ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process 05000346/LER-1998-010, :on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with1998-10-26026 October 1998
- on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with
ML20154D4191998-10-0505 October 1998 Safety Evaluation Supporting Amend 227 to License NPF-3 05000346/LER-1998-008, :on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With1998-10-0101 October 1998
- on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With
ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-007, :on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With1998-09-22022 September 1998
- on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With
ML20151U0251998-09-0202 September 1998 Safety Evaluation Supporting Amend 226 to License NPF-03 ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With 05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources1998-08-21021 August 1998
- on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 05000346/LER-1998-004, :on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired1998-07-13013 July 1998
- on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired
05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations1998-07-11011 July 1998
- on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations
ML20236M9411998-07-0707 July 1998 Safety Evaluation Supporting Amend 225 to License NPF-3 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 1999-09-30
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U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 366 (7 77)
LICENSEE EVENT REPORT (PLE ASE PRINT 081 TYPE ALL REQUIRED INFORMATION)
CONTROL BLOCK l 1
l l l l l lh 6
1 lj1l1l@l l lg lo l1l 7 8 9 l 0] LICENSEE Hj DjCODE Bl Sl 1lglS0 l0 l- l0LICENSE 14 I l0 lN lP lF l- l0 l3 jgl4 NUM8EH 25 26 LICENSE TY PE JG 51 C A T $8 CON'T L@l l5 l0DOCKET l- [0 l3 l4 l6 }@l 01 21 0 ! 5l 7 l 9 l@l 0REPORT l 2 lDATE 2 l 8 l807 l 9 l@
"E OA l0l1l 3o(,pC 60 61 NUYSER 6d 63 EV"NT D ATE 74 75 7 8 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l ITTTl i At 1807 hours0.0209 days <br />0.502 hours <br />0.00299 weeks <br />6.875635e-4 months <br /> on 2/5/79, Containment High Pressure Alarms were received and Safety
[ o l a l l Features Actuation System (SFAS) Channel 2 tripped f rom an erroneous containment high l l o l 4 l l pressure signal. The duration of the high pressure signal was less than one second. 1 l
O s l During this time the unit was placed in Action Statement 9 of Tech Spec 3.3.2.1.
The l l o 16 I l There was no danger to the health and safety of the public or unit personnel.
l 0 7 l bistable tripped icmediately, and the three remaining SFAS containment high 0 a 1 pressure instrument strings were operable. (NF-33-79-26) _!
80 SUBCO E COMPONENT CODE SUBC DE SU ODE C DE CODE I O_L]
8 l Il Bj@ l Xl@ [ X l@ lX XlXlX 9 to 11 12 13 X lX l@ {@ ]@
16 19 20 7
REPORT REVISION SEQUENTI AL OCCURRENCE CODE TYPE NO.
EVENT YEAR REPORT NO.
O ,agg LER RO 17191 l- 10 2 l1 l l-l le l3 l l tl l_] l0 l u 28 2') 33 31 32 22 23 24 26 27
_ 21 HOURS 22 IT$IO FOR 1 B. SU PLIE MAN FA TURER AKE A x;
ON PL NT gg . Tzlg 0 ;0 0 hr ; SS8gg in ;g x g ;x ; x; x xg 33 x jg;34T O'g 35 36 3/ 40 41 42 43 44 47 CAUSE DESCRIPTON AND CORRECTIVE ACTIONS gi;ogjNo specific cause has been found for the momentary spike in containment pressure. Thel Both I ji ;ijl instrument st ring was inspected but the cause of the spike was not discovered.
I g g the monthly a nd refueling surveillance tests were performed but no deficiencies were l
- ,,3; gdiscovered. The channel was returned to operation.
l 1 4 l 80 7 8 9 OTHER STATUS ISCO RY DISCOVERY DESCRIPTION STA S *6 POWER
[1_l,5_j @ l0 l8 l7 l@] NA l lAj@l NA l ACTIVITY CONTENT LOCATION OF RELEASE RELE ASED OF RELEASE AMOUNT OF ACTIVITY
@ NA l l NA l 7
1 6 8 9 10
@l 11 44 45 80 PERSONNEL EXPOSURES NUV8ER TYPE DESCRIPTION NA I LLLLI I 01 01 0_]@l zl@l "
,ERSONNELINJES NUYBER DESCRIPTION l
I IB8 I9 e 7
0 01 @ l12 11 NA 80 LOSS OF OR DAYAGE TO FACILITY .
TYPE DESCRIPTION NA l i o I zi@l10 80 7 8 9
'"" 7003QM +, 790306047 NRC USE ONLY ,
,SSUl[@ollCR,,nON@' ll[]lllllllllj 2 O IN l NA 68 69 80 7.
t1 9 to W4NW,M.m{
i DVR 79-030 ,,., , ,,n PAnen Susmi A. Kovach pggyg_.
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLE! ENTAL INFORMATION FOR LER NP-33-79-26 DATE OF EVENT: February 5, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Safety Features Actuation System (SFAS) Channel 2, containment high pressure trip Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) = 2406.2, and Load (Gross MWE) = 785. .
Description of Occurrence: At 18:07:52 hours on February 5,1979, Containment High Pressure Alarms P311 and P899 were received and Safety Features Actuation System (SFAS) Channel 2 tripped from an erroneous containment high pressure signal
( > l8.4 psia) . The duration of the high pressure signal was less than one second.
During this time, the unit was placed in Action Statement 9 of Technical Specifica-tion 3.3.2.1. Technical Specification 3.3.2.1 requires all four containment high pressure SFAS channels to be operable in Modes 1, 2, and 3. Action Statement 9 allows operation to proceed provided the inoperable channel is placed in the tripped condition within one hour and the remaining three containment high pressure instrument strings are operable.
Designation of Apparent Cause of Occurrence: No specific cause has been found for the momentary spike in containment pressure. Under Maintenance Work Order I&C-167-79 the instrument string was inspected but the cause of the spike was not discovered.
Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. The bistable tripped immediately and the three remaining SFAS containment high pressure instrument strings were operable.
Corrective Action: At 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br /> on February 5,1979, Surveillance Test ST 5031.01,
" SEAS Monthly Test" on SEAS Channel 2 was successfully completed to verify operabi-lity. Surveillance Test ST 5031.03, " Containment Pressure Inputs to SFAS Refueling Calibration" was performed on February 15, 1979 for further investigation but no deficiencies were discovered. Since the trip was of such a short duration and there have been no previous SFAS channel containment high pressure trips, no correc-tive action other than continuing to monitor this problem can be taken. Should this problem become repetitive, further investigation will be carried out.
Failure Data: There has been no previous reported occurrence of an SFAS channel containment high pressure trip.
LER #79-021