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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20236U5011998-07-23023 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 ML20115J1121996-07-17017 July 1996 Voluntary Report:On 960430,two Unplanned Starts of Emergency Diesel Generator (EDG) 1-2 Occurred.Caused by Failure to Perform Procedural Step to Verify Power Supply to Electrical Busses D1 & D2.Personnel Counseled ML20071K6881994-07-27027 July 1994 Special Rept:On 940519,pilot Operated Relief Valve Opened for Approx 5 Seconds During Functional Testing of Replacement Reactor Trip Module in Reactor Protection Sys ML20118B9951992-10-0202 October 1992 Ro:On 920910,discovered That non-TS Hourly Fire Watch, Completed on 920908,improperly Performed,Per Suppl 1 to NRC Bulletin 92-001,resulting in Falsification of Fire Watch Log.Individual Disciplined & Addl Training Provided ML20096H0261992-05-19019 May 1992 Special Rept:On 911206,twelve Smoke Detectors in Fire Detection Zone Were Inoperable.Cause Unknown.Detectors Replaced W/Pyrotronics Model DI-6 ML20094L0651992-03-19019 March 1992 Special Rept:On 920204,local Fire Detector Alarm Panel for Fire Detection Zone Was in Trouble Indication Condition. Cause Not Determined.Hourly Fire Watch Patrol Established to Monitor Alarm ML20086K3891991-12-0606 December 1991 Supplement to 910925 Special Rept:On 910830,four Addl Alison Controls,Inc Detectors in Fire Detection Zone RCP-1,RCP-3, RZP-4 & Fdz A208 Failed.Caused by Dust Particles in Sensing Chamber.Subj Detectors Replaced W/Pyrotronics Model DI-6 ML20079F6301991-09-25025 September 1991 Special Rept:On 910818 & 0905,Fire Detection Zone A208 & Instruments Declared Inoperable When Subj Zone Panel Went Into Alarm W/No Indications of Fire.Detector Shipped to Vendor for Troubleshooting & Repair ML20073Q7671991-05-29029 May 1991 Special Rept:On 910415,ionization Type Fire Detector in Fire Detection Zone 235 (Boric Acid Evaporator Room 1-1) Inoperable.Ts 3/4.3.3.8 Entered & Hourly Fire Watch Patrol Established within 1 H ML20072U8091991-01-10010 January 1991 Special Rept:On 910304,electric Fire Pump Removed from Svc for Planned Outage for More than Seven Days.Pump Removed to Replace Existing Controller.Replacement of Controller Accomplished & Electric Fire Pump Returned to Svc ML20058M8561990-08-0606 August 1990 Ro:On 900609 & 11,station Experienced Series of Events Which Lead to Opening of Control Rod Drive Trip Breakers.Caused by Fuse Failure & Mispositioned Control Mode Selector Switch, Respectively.Test Procedure Being Modified ML20246K8931989-07-14014 July 1989 Ro:On 890314,discovered Error in Scheduling & Actual Performance of Surveillance Requirement 4.6.1.3 Re Testing for Personnel & Emergency Air Locks.Caused by Oversight. App J Exemption Request Submitted & Test Interval Changed ML20154C5271988-08-31031 August 1988 Special Rept:On 880722,Tech Spec 3.3.3.3 Violated.Caused by Accelerometers Being Inoperable for More than 30 Days.Mod 88-0060 to Replace Accelerometers Scheduled for Completion by 880915 ML20154M6751988-05-26026 May 1988 Special Rept:On 880419,diesel Fire Pump Removed from Svc for Maint & Declared Inoperable for Longer than Limit Required by Tech Spec Due to Unanticipated Temp Switch Failure.Switch Repaired & Diesel Fire Pump Declared Operable ML20236L4361987-11-0606 November 1987 Special Rept:On 870718,fire Detection Zone FDZ-A208 Declared Inoperable.Caused by Failure of Fire Detector.Hourly Fire Watch Established.Main Work Order Initiated to Repair Detector ML20236S8411987-06-12012 June 1987 Special Rept:On 870513,fire Protection Coordinator Discovered Damage to Fire Barrier Wall in Entrance to Radiation Access Control Area.Probably Caused by Personnel Negligence.Repairs to Wall Should Be Completed by 870731 ML20235B7741987-01-21021 January 1987 RO 07352:on 870121,reactor Tripped from 40% Power.Cause Not Yet Known & All Sys Functioned as Regulated for Reactor Trip ML20076J7391983-06-27027 June 1983 Ro:On 830616,hatches Associated W/Negative Pressure Boundary & Fire Barrier Removed.Notification Satisfies 30-day Requirement.Written Rept Will Be Submitted by 830713 ML20054E1931981-10-16016 October 1981 Telecopy RO Re Max String Error of Pressure/Temp Bistable of Reactor Protection Sys Exceeding Allowable Values of Tech Spec 2.2.1,Table 2.2-1.Event Reported on 811016.Facility Change Request Implemented 1998-07-23
[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 ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.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 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 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 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 ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 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 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 ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.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 ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With 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 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A4121998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20196B5221998-05-23023 May 1998 10CFR50.59 Summary Rept of Facility Changes,Tests & Experiments Dbnps,Unit 1 for 960602-980523 ML20236E7581998-05-19019 May 1998 Rev 0 to Davis-Besse Unit 1 Cycle 12 Colr ML20236N7501998-04-30030 April 1998 Rev 2 to Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit ML20247F6721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Davis-Bess Nuclear Power Station,Unit 1 ML20249A4141998-04-30030 April 1998 Revised Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20216B4041998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20216C5131998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20202D3721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20199G6321998-01-26026 January 1998 Rev 1 to Davis-Besse Unit 1,Cycle 11,COLR ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20198K7931997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20217K6401997-12-31031 December 1997 1997 Annual Rept First Energy ML20203A3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Davis-Besse Nuclear Power Plant,Unit 1 ML20198S5371997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Davis-Besse Nuclear Power Station ML20217H7701997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20216H3261997-08-31031 August 1997 Monthly Operating Rept for August 1997 for DBNPS ML20217K0241997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Davis Besse Nuclear Power Station,Unit 1 1999-09-30
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TOLEDO 1 EDISON r
July 14, 1989 . Log No.: KA89-40017 NP-33-89-006 L
w Docket.No. 50-346 ^
License No. NPF-3 United States Nuclear Regulatory Commission Document Control Desk ,
Washington, D. C. 20555 Gentlemen:
i Davis-Besse Nuclear Power Station, Unit No. 1 Date of Occurrence - March 14, 1989
-Enclosed is a Voluntary Report which is being submitted per NUREG-1022, Supplement 1.
Yours truly, d.
M&n '
Louis F. Storz-Plant Manager Davis Besse Nuclear Power Station LFS/p1g Enclosure cc: Mr. A. Bert Davis.
Regional Administrator USNRC Region III Hr. Paul Byron DB-1 NRC Resident Inspector B907180293 890714 P PDR ADDCK 05000346 S PNU
((2. 2, THE TOLEDO ED! SON COMPANY EDtSON PLAZA 300 MADISON AVENUE TOLEDO OHIO 43652 /
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NRC Form ans ' U.S. NUCLEAM KECULATESY COMMitBIOes
, APPROYED OMt NO 3191LO104 LICENSEE EVENT REPORT (LER) (KPIRE81/2W 71CILITY NAME (18 DOCKET NUMBER t!) PAGE(3)
I Davis-Besse Unit No. 1 015 l 0 t o l 0 l 3l4 l6 -ii jopl 0l 3 TITLE tes Appendix J Testing of Air Locks Not Per Code Frequency Requirement EVENT DATE tel LgR NvMsER gai RgPORY DATE 17) OTHER F ACILITIES INVOLVED 'SI m F AC8 LIT Y **AMES DOCKET NUMBER (8)
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NAME TELEPHONE NUMBER AREA CODE .
Jan C. Stota. Engineer - Maintenance Planning 411 19 21419 l- l 5101010 COMPLETE ONE LINE FOR EACH COMPONENT F AILURE DESCRIBED IN THIS fitPORT (13) i CausE sv TEM COwO sNT "*lg;;c. aygRyAggE ,
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i On March 14, 1989, as a result of a Technical Specification Verification Program review meeting, it tas recognized that the scheduling and actual performance of the Surveillance Requirement 4.6.1.3 testing for the Personnel ]
, and the Emergency Air Locks was in error. The Technical Specifications
- l. allowed the use of Surveillance Requirement 4.0.2 which allovs'the 1.25/3.25 criterion to be used. This allowed stretch was used. 10CFR50, Appendix J l does not address the use of test interval stretches. The difference vas an apparent oversight then the Technical Specifications were originally submitted I to the NRC. Toledo Edison should have submitted a specific exemption to the ;
NRC. There is no afety significance to this finding. The basic test .
, intervals are maintained. The test interval was reduced on March 14, 1989, to j l assure compliance >ith Appendix J. Teshnical Specification Surveillance Requirements were reviewed to identify any other conflict in frequency requirements between Technical Specifications and other regulations. No other such conflicts were found. An exemption to Appendix J vas submitted on July 5, 1989.
This is being submitted as a Voluntary Report.,
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION amoveo ous No. siso-om exma s. siain F ACILITY NAME til DOCKET NUMBER (21 ggg gygggg(g) PAGE (3) vsaa " W J'.',' 4'J#.?R I
' Davis-Besse Unit No. 1 0 l5 l0 l0 l0 l 3l4 l 6 l l l g 0g2 or 0l3 YlKT Uf more space 40 moowest, use entane!NRC Fems an6Kal(1T)
Description of Occurrence:
On March 14, 1989, as a result of a Technical Specification Review Pregram l review meeting, it'vas recognized that the scheduling of the Surveillance Requirement 4.6.1.3 testing for the Personnel and Emergency Air Locks was in error. The scheduling system was using the . surveillance Requirement.4.0.-2 which allowed 1.25/3.25 stretch when determining Technical Specification late dates. 10CFR50, Appendix J, does~not include the use of test interval stretches,. - Toledo Edison had not applied for an exemption to the code requhement to allow the use of Technical Specification 4.0 2. However, .
Surveillance Requirement 4.6.1.3 does allow the use of Surveillance Requirement 4.0.2, as written. Therefore, Toledo Edison has been using Surveillance Requirement 4.0.2 for scheduling and actual test performance without having received an approved exemption from the NRC, This 'linding is being submitted as a Voluntary Report.
Apparent Cause of Occurrence:
The air lock testing has been scheduled this way since startup of the plant in 1977. The scheduling system uses 4.0.2 for this test requirement because Technical Specification 3.6.1.3, as written, allows it. The oversight occurred when the Technical Specifications were originally written. Toledo Edison should have submitted a specific exemption request with the submittal of the Technical Specifications.
l Analysis of Occurrence:
There is no safety significance to this finding. Surveillance ~ Requirement 4.0.2 provides a reasonable scheduling tool which limits the amount of extension between any two tests to 25 percent of the test interval and also no more than a total of 25 percent stretch over three t'onsecutive test intervals.
For a six-month test interval, the stretch allowed would be 1.5 months, which has no significance in relation to LOCA frequency and other post-accident impact.
Correcti.e Actions The test interval for S1 5061.02, the six-month test # air locks, was changed by March 14, 1989, to eliminate the use of SurveillaM P2quirement 4.0.2.
l A review of thr, Technical Specification Surveillance Requirements has been l I
conducted to identify any other conflicts in frequency requirements between Technical Specifications and other regulations. The only discrepancy identified was between Surveillance Requirement 4.6.1.3.a r.nd b and Appendix J l of 10CFR50, the subject of this rtuort. !
1 An exemption to Appendix J was subs.it ted to the NRC on July 5,1989, to justify use of Surveillance Requirement 4.0.2.
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_ _ . _ _________.______.__._._._._J
Nec Form ac4A US. NUCLEAR f'EIULATDr.V COMMtssiON
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- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPzoveo oms No. sino-oso.
EXPl%E5.8!31E3 F AC4LITY NAME 11) DOCKET NUMBER (2) LER nut 485R 16) PAGE (3) vs*a "0LW, "'ut*.?
i Davis-Besse Unit No. 1 o p l0 l0 l0 l3 l 4;6 g _ gg _
g O3g op 0 g3 TQXT 12 more spear n reeuwent, une sowoonelNMC Fam,386A'st 111>
Failure Datat This is the first report of Technical Specification Surveillance Requirement, as written, not being in compliance with the codes that they were intended to i meet.
1 REPORT NO: NP 33-89-006 PCAO NO: 89-0150 N#C eORU 3ase 9 43:
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