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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEAR2CAN119504, Special Rept Re SG Tube Surveillance Category C-3 Results1995-11-13013 November 1995 Special Rept Re SG Tube Surveillance Category C-3 Results 0CAN079502, Special Rept:On 950608,electric Fire Pump P-6A Declared Inoperable.Cause of Degraded Performance Indeterminate at Time But Believed to Be Result of Normal Wear.Temp Fire Pump for Backup Fire Suppression Water Supply Installed1995-07-14014 July 1995 Special Rept:On 950608,electric Fire Pump P-6A Declared Inoperable.Cause of Degraded Performance Indeterminate at Time But Believed to Be Result of Normal Wear.Temp Fire Pump for Backup Fire Suppression Water Supply Installed 1CAN109302, Special Rept:On 930922,EFP P-6A Exceeded AOT of Seven Days Due to Mod Work on 4,160 Volt Bus A-1.Power to non-vital Bus A-1 Restored on 930922 & Weekly Surveillance on EFP P-6A Performed Satisfactorily on 9309231993-10-14014 October 1993 Special Rept:On 930922,EFP P-6A Exceeded AOT of Seven Days Due to Mod Work on 4,160 Volt Bus A-1.Power to non-vital Bus A-1 Restored on 930922 & Weekly Surveillance on EFP P-6A Performed Satisfactorily on 930923 2CAN049107, Special Rept:On Eighth Refueling Outage,Consisting of Insp of Steam Generator.Insp Revealed Three Defective Tubes in B Steam Generator & No Defective Tubes in a Steam Generator.Condenser Tubing Routinely Cleaned1991-04-0505 April 1991 Special Rept:On Eighth Refueling Outage,Consisting of Insp of Steam Generator.Insp Revealed Three Defective Tubes in B Steam Generator & No Defective Tubes in a Steam Generator.Condenser Tubing Routinely Cleaned 2CAN019101, Special Rept:On 901219,fire Pumps Inoperable During Performance of Surveillance Test.Method of Performing Surveillance Procedure Will Be Revised by 9103011991-01-0202 January 1991 Special Rept:On 901219,fire Pumps Inoperable During Performance of Surveillance Test.Method of Performing Surveillance Procedure Will Be Revised by 910301 0CAN129002, Special Rept:On 901026,fire Pump Inoperable for More than 7 Days.Temporary Pump Installed as Backup1990-12-0303 December 1990 Special Rept:On 901026,fire Pump Inoperable for More than 7 Days.Temporary Pump Installed as Backup 1CAN119012, Special Rept:On 901022,Unit 1 Control Room Halon Sys Inoperable for More than 14 Days Due to Removal of Ceiling Tiles in Auxiliary Control Room for Installation of Conduit Pulling of Cables.Operability Restored on 9011061990-11-21021 November 1990 Special Rept:On 901022,Unit 1 Control Room Halon Sys Inoperable for More than 14 Days Due to Removal of Ceiling Tiles in Auxiliary Control Room for Installation of Conduit Pulling of Cables.Operability Restored on 901106 2CAN089008, Voluntary Rept 50-368/90-V01-00:revises Completion Date for Commitment Date in Voluntary Rept from 900801 to 900831 Re Inadvertent Starting of Emergency Diesel Generator While Attempting to Air Roll Engine During Maint1990-08-0303 August 1990 Voluntary Rept 50-368/90-V01-00:revises Completion Date for Commitment Date in Voluntary Rept from 900801 to 900831 Re Inadvertent Starting of Emergency Diesel Generator While Attempting to Air Roll Engine During Maint 2CAN089010, Voluntary Rept 50-368/90-V02-00 Re Result of Postulating Failure of Check Valve in LPSI Sys Not Previously Postulated.Caused by Higher Differential Pressure Not Considered.Valve Mfg Consulted1990-08-0303 August 1990 Voluntary Rept 50-368/90-V02-00 Re Result of Postulating Failure of Check Valve in LPSI Sys Not Previously Postulated.Caused by Higher Differential Pressure Not Considered.Valve Mfg Consulted 2CAN098905, Special Rept 50-368/89-013-00 on 890626,pressurizer Level Decreased While Flushing Header C of LPSI Sys.Caused by Backleakage Through Header Safety Injection Check Valve.Hpsi Pump Started & Valve Opened to Inject Water Into RCS1989-09-23023 September 1989 Special Rept 50-368/89-013-00 on 890626,pressurizer Level Decreased While Flushing Header C of LPSI Sys.Caused by Backleakage Through Header Safety Injection Check Valve.Hpsi Pump Started & Valve Opened to Inject Water Into RCS 05000313/LER-1986-002, Requests Extension Date of 860930 to Allow Time to Update LER 86-002-00 Re Inadequate 10CFR50.59 Design Change Review1986-08-19019 August 1986 Requests Extension Date of 860930 to Allow Time to Update LER 86-002-00 Re Inadequate 10CFR50.59 Design Change Review 2CAN078504, Ro:On 850410,unmonitored Release of Radioactive Water Into Oily Water Separator Occurred.Caused by Inadvertent Opening of HX Drain During Maint Insp.Drain Closed After Approx 3 H. Dardanelle Reservoir Unaffected.Personnel Counseled1985-07-11011 July 1985 Ro:On 850410,unmonitored Release of Radioactive Water Into Oily Water Separator Occurred.Caused by Inadvertent Opening of HX Drain During Maint Insp.Drain Closed After Approx 3 H. Dardanelle Reservoir Unaffected.Personnel Counseled 2CAN068508, Ro:On 850529 high-range Containment Radiation Monitor 2RITS-8925-2 Discovered Failed Low.Redundant Monitor 2RITS-8925-1 Verified Operable.Caused by Open Circuit in Signal & High Voltage Cable Connectors.Connectors Replaced1985-06-28028 June 1985 Ro:On 850529 high-range Containment Radiation Monitor 2RITS-8925-2 Discovered Failed Low.Redundant Monitor 2RITS-8925-1 Verified Operable.Caused by Open Circuit in Signal & High Voltage Cable Connectors.Connectors Replaced 1CAN108305, Ro:On 831013,single Battery Cell in One Bank of Batteries Found Unacceptable & Declared Inoperable.Util Application of 3.7.2 Series of Specs Discussed1983-10-21021 October 1983 Ro:On 831013,single Battery Cell in One Bank of Batteries Found Unacceptable & Declared Inoperable.Util Application of 3.7.2 Series of Specs Discussed ML20054D8561982-04-16016 April 1982 RO 50-368/82-011:on 820415,leak Discovered Inside Containment in Steam Generator B Blowdown Line Between Valve 2CV1065 & Containment Penetration.Unit Shut Down.Blowdown Line Will Be Repaired ML20064H4491978-12-14014 December 1978 RO 50-368/78-17 on 781201:Emergency Feedwater Train B Response Time Was Less Conservative than Assumed in the Safety Analysis Due to Unknown Cause.Emergency Feedwater Train B Reset to a Valve Consistent W/Safety Analysis 1995-07-14
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30
[Table view] |
Text
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I- Reportable Occurrence Report No. 50-368/78-17
- 2. Report Date: December 14, 1978 3. Occurrence Date: December 1,1978 4 Facility: Arkansas Nuclear One-Unit 2 Russellville, Arkan;as
- 5. Identification of Occurrence:
During Mode 3 operation, prior to initial criticality, it was determined that the response time for Emergency Feedwater Train B, as listed in T. S. Table 3.3-5 Items 7B & 88,was less conservative than that assumed in the Safety Analysis. There have been two previous similar occurrences (see 50-368/78-14 and 50-368/78-10). j l
- 6. Conditions Prior to Occurrence:
Steady-State Power Reactor Power 0 MWth c
Hot Standby X Net Output 0 Mwe Cold Shutdown Percent of Full Power 0 g Refueling Shutdown Load Changes During Routine Power Operation 0 Routine Startup Operation Routine Shutdown Operation f
other (specify) Mode 3 operation before initial criticality
/
- 7. Description of Occurrence:
The EFW Train B setpoint as specified in T. S. Table 3.3-5 Items 78 &
88 was found to be less conservative than assumptions used in the Safety Analysis.
78122002 @ 23
Reportabic Occurrence Report No. 50-368/78-17 S. Designation of Apparent Cause of Occurrence:
Design Procedure Manufacture Unusual Service Condition Including Environmental Installation /
Construction Component Failure (See Failure Data)
Operator Other (specify) Delayed communication between NSSS vendor and AE while performing reanalysis of the EFW and associated elec-trical systems.
- 9. Analysis of Occurrence: ,
Since the reactor core had not been made critical, the nonconservative set-point did not endanger the health and safety of the public as the plant had never been operated in a mode wh.ich would require EFW to control or mitigate a postulated accident.
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Reporta'ule Occurrence Report No. 50-368/78-17
- 10. Corrective Action:
Upon discovery of the nonconservative setpoint, the setpoint was changed to a value within the assumptions of the Safety Analysis.
A new analysis has been perfonned which substantiates the. values that currently exist in the Technical Specifications.
5
- 11. Failure Data:
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