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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARRA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review1997-12-19019 December 1997 LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review 05000261/LER-1983-005, Supplemental LER 83-005/01T-1:on 830424,svc Water Booster Pump B Declared Inoperable Due to Loss of Bearing Oil.Caused by Bearing Oil Slinger Positioned Near Vent Holes.Standpipes Installed on Each Vent Hole1984-06-14014 June 1984 Supplemental LER 83-005/01T-1:on 830424,svc Water Booster Pump B Declared Inoperable Due to Loss of Bearing Oil.Caused by Bearing Oil Slinger Positioned Near Vent Holes.Standpipes Installed on Each Vent Hole 05000261/LER-1980-030, Updated LER 80-030/03L-1:on 801202 & 03,charging Pumps A,B & C Discharge Line Pressure Gauge Tap Pipe Socklets Found Leaking.Caused by Sys Design Deficiencies Allowing High Vibration.Leaks Repaired & Design Modified1983-09-30030 September 1983 Updated LER 80-030/03L-1:on 801202 & 03,charging Pumps A,B & C Discharge Line Pressure Gauge Tap Pipe Socklets Found Leaking.Caused by Sys Design Deficiencies Allowing High Vibration.Leaks Repaired & Design Modified 05000261/LER-1981-001, Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised1982-11-17017 November 1982 Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised 05000261/LER-1980-027, Updated LER 80-027/01T-1:on 801122,relay RT-9 in Reactor Protection Train a Failed to re-energize During Periodic Test of Reactor Protection Logic.Caused by Shorting of Lead Wire Connection to Coil Wires.Relay Replaced1982-10-11011 October 1982 Updated LER 80-027/01T-1:on 801122,relay RT-9 in Reactor Protection Train a Failed to re-energize During Periodic Test of Reactor Protection Logic.Caused by Shorting of Lead Wire Connection to Coil Wires.Relay Replaced 05000261/LER-1981-002, Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modifie1982-08-20020 August 1982 Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modified 05000261/LER-1976-014, Updated LER 76-014:on 760805,util Notified by NRC That Peak Clad Temp Increase Presented by Westinghouse Should Be 50 F Higher.Caused by Using Different Versions of ECCS Model. New Limit in Effect 750825.W/760917 Ltr1976-09-17017 September 1976 Updated LER 76-014:on 760805,util Notified by NRC That Peak Clad Temp Increase Presented by Westinghouse Should Be 50 F Higher.Caused by Using Different Versions of ECCS Model. New Limit in Effect 750825.W/760917 Ltr 1997-12-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A1691999-09-22022 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 RA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review1997-12-19019 December 1997 LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20217Q2751997-06-30030 June 1997 CP&L Fitness for Duty Program Performance Data for Period 970101-0630 ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20079H1571991-09-30030 September 1991 Nonproprietary Evaluation of Revised Transfer to Cold Leg Recirculation Procedure,Hb Robinson Unit 2 ML20086T2951991-06-14014 June 1991 Rev 1 to EQ Documentation Package Eqdp 36.0, Boston Insulated Wire Cable ML20086T2861991-03-0808 March 1991 Rev 1 to EQ Documentation Package Eqdp 11.1, Dekoron Instrumentation Cables ML20086T2561991-03-0808 March 1991 Rev 1 to EQ Documentation Package 10.0, Continental Shielded Instrument Cable ML20065K6961990-10-31031 October 1990 Mechanical Licensing Rept for Hb Robinson High Thermal Performance Fuel Assemblies ML20065K6971990-10-31031 October 1990 Thermal Hydraulic Compatibility Analysis of Anf High Thermal Performance Fuel for Hb Robinson,Unit 2 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20247E0701989-07-20020 July 1989 Info Rept:On 890717-0804,fire Penetration Seals Will Be Removed from Svc to Allow Access for Ventilation Sys Mod. Addl Fire Barrier Penetrations Will Be Made in Wall Between RHR Pump Pit & Fuel Handling Bldg,Per Tech Spec 3.14.7.2 ML20246E9111989-03-31031 March 1989 PDC-3:Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2 ML20245H0821989-01-25025 January 1989 Criticality Safety Analysis of Hb Robinson Spent Fuel Pool W/4.2% Nominal Enrichment Fuel Assemblies ML20205T0551988-10-31031 October 1988 Responses to NRC Questions on RTD Bypass Elimination Licensing Rept ML20147E2371988-02-29029 February 1988 1987 Annual Rept - Primary Coolant Iodine Spikes ML20147B1971987-12-31031 December 1987 1987 Annual Rept - Primary Safety & Relief Valve Challenges ML20236K7731987-10-31031 October 1987 Monthly Operating Rept for Oct 1987 ML20235W3781987-09-30030 September 1987 Monthly Operating Rept for Sept 1987 ML20238E2741987-08-31031 August 1987 Monthly Operating Rept for Aug 1987 ML20235H3151987-06-30030 June 1987 Monthly Operating Rept for June 1987 ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20214W3241987-05-31031 May 1987 Monthly Operating Rept for May 1987 ML20214R5101987-04-30030 April 1987 Rev 1 to Monthly Operating Rept for Apr 1987,correcting Operation Statistics & Shutdown Experience Due to Mathematical Errors ML20215L4941987-04-30030 April 1987 Monthly Operating Rept for Apr 1987 ML20206F3561987-03-31031 March 1987 Monthly Operating Rept for Mar 1987 ML20210B4141987-03-31031 March 1987 Revised Monthly Operating Rept for Mar 1987 ML20205F6021987-03-23023 March 1987 Special Rept:On 870302,noble Gas Effluent Monitor for Main Steam Line B Declared Inoperable & Svc Not Returned Until 870312.Caused by Defective Detector.Detector Replaced.High Voltage for Detector Adjusted & Sys Operation Checked ML20212P3101987-02-28028 February 1987 Monthly Operating Rept for Feb 1987 ML20214Q7891987-01-31031 January 1987 Cycle 12,SAR ML20210R6341987-01-31031 January 1987 Monthly Operating Rept for Jan 1987 ML20207M2451986-12-31031 December 1986 Monthly Operating Rept for Dec 1986 L-18-120, Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi1986-12-18018 December 1986 Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi ML20215C7911986-11-30030 November 1986 Monthly Operating Rept for Nov 1986 ML20213F3121986-10-31031 October 1986 Monthly Operating Rept for Oct 1986 ML20215G1081986-09-30030 September 1986 Monthly Operating Rept for Sept 1986 ML20215F0361986-09-29029 September 1986 Special Rept:On 860902,during Cold Shutdown,Pressurizer PORV Lifted Twice to Prevent Overpressurization.Caused by Inadvertent Action by Unit Operators.Operations Personnel Counseled Re Importance of Breaker Position Indicators ML20211C0641986-09-0909 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson Spent Fuel Storage Racks (Unpoisoned,Low Density) W/4.2% Enriched 15x15 Fuel Assemblies ML20211C0491986-09-0202 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson New Fuel Storage Vault W/4.2% Enriched 15x15 Fuel Assemblies ML20212F5321986-07-31031 July 1986 Monthly Operating Rept for Jul 1986 ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20202G3371986-06-30030 June 1986 Monthly Operating Rept for June 1986 ML20211B5601986-05-31031 May 1986 Monthly Operating Rept for May 1986 ML20197D2651986-04-30030 April 1986 Monthly Operating Rept for Apr 1986 1999-09-22
[Table view] |
LER-2076-014, Updated LER 76-014:on 760805,util Notified by NRC That Peak Clad Temp Increase Presented by Westinghouse Should Be 50 F Higher.Caused by Using Different Versions of ECCS Model. New Limit in Effect 750825.W/760917 Ltr |
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1Jp'didkeport: HBR2 R0-76-14 (1)
Previous Report Date: 8-19-76 QENSEE EVENT REPORT O .
CONTROL BLOCK:l l l l l l l [PLEASE PRINT ALL EgeumE3 INFOIMATION) 1 8
"* YPE
'S'AM E LCENSE NUMBER O l S l C l Hl Bl Rl 2l . l 0 l 0 l-l 0l 0l 0l0 l0 l-l 0 l 025l [4] 1l 1l 1l 0l l0 l1l 14 15 2E 30 31 32 7 89 CATEceav "'E EE T coCui NuMeEn EvtNT oATE REPORT DATE QCON'T l l l (_7] [L_) l 0 l 5 l O l-l 0l 2l 6l ll l0 l 8 l 0 l 5 l 7l 6l l 0 l 9 l ll 7l 7l 6l 58 59 60 61 68 69 74 75 80 7 8 57 EVENT DESCRIPTION HE l On August 24, 1976 Carolina Power & Light was notified by NRC that the Peak Clad l 7 89 80
@l Temperature (PCT) increase which Westinghouse presented to the individual utilities l 80 7 89 3[ l should be 500 F higher due to use of different versions of the ECCS when making the l 7 89 80
@l comparison of PCT. This increase in PCT results in a reduction of the' limiting Fn l '
7 89 ~
80 l
EG l for Robinson 2 to 2.05.
80 7 89 pque C E M ACR M R v0LATON COCE COMPONENT CODE M l Zl Z l W 7 89 10 11 l Zl Zl Z]Z ] Z l Zl 12 17 W 43 lZ l9 l9 l9 l 44 47 W 48 CAUSE DESCAiPTION B0 l Westinghouse used a different version of the ECCS model when evaluating the effects l 7 89 80 7 89 to PCT of T..
auc versus T_ vuw
.. for the U' head fluid temoerature (Ref: HER 2 R0-76-14). l 80
@l This res.q1ted in an indicated increase in PCT of 50 F less than that value which l status % POWER CTHER bfATUS OSCOVER DiSCOvFRY DESCAIPTON i
7 8
[f,.]
9 l1l0l0l l 10 12 13 N/A 44 l b45 l 46 Notification 80 l
AELE SFD OF AMOUNT OF ACitVITY LOCATCN OF AELEASE E (_Z_j 9
(Z_]EL ASE 10 lN/A l 44 l
45 N/A eo l
7 8 11 ,
PERSONNEL EXPOSURES DE105101 7 89 11 bI12 13 N/A .
80 l
PERSONNEL INJURIES Nu"BE R CESCAlPTON h l0 l0! 0l 7 89 11 12 l N/A 80 l
OFFSITE CONSEQUENCES gg l N/A .
j 7 89 -
80 LOSS OR DAMAGE TO FACluTY Tv Pf DE SCPIPT ON 3 [_j l N/A l PUBUC TY 2010186 760917 N/A g ADOCK 05000261 3 l
1 l PDR 7 89 80 ADDITIONAL FACTOAS
@l 7 89 Cause Description cont'd... results when using the same version for both temperatures l.
80 gl The new limit was placed in effect August- 25, 1975. l NAME: PHONE:
803-332-1351 y' ... ......,
n b3 U i
l l
September 17, 1976 FILE: NG-3513 (R) SERIAL: NG-76-1252 Mr. Norman C. Moseley, Director U. S. Nuclear Regulatory Commission Region II, Suite 818 230 Peachtree Street, N.W.
Atlanta, Georgia 30303
Dear Mr. Moseley:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET 50-261 LICENSE NO. DPR-23 UPDATE FOR LICENSEE EVENT REPORT 76-14 Attached for your consideration is an update to Licensee Event Report 76-14. This update relates the requirement to further reduce FQ to 2.05. Since this event is a continuation of the original occurrence, this report is treated as an update.
This report is in accordance with the format set forth in Regulatory Guide 1.16, Revision 4.
Yours very.truly,
,- ) y, ,
c 4.- -,
- ,/ a 'yd . v . - pr A't-4 H. R. Banks Manager Nuclear Generation e" , i
??
CSB:bb /)J .,
li: -
Attachment .- 'C,7W i a OCI2 >-
y cc: Messrs. W. G. Mcdonald L{b
\ . u.5.";[OE$ M)
E. Volgenau D ~*****
NM :
i 9S94 i COPY SENT REGI -