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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20151C1931975-12-19019 December 1975 AO 20-75:on 751218,30-inch Ventilation Pipe Contacted by Power Showel During Const Activity.Caused by Inadequate Administrative Controls Re Preparation & Review of Const Activity.Work Activity Stopped.Engineering Review Requested ML20151C1951975-11-0606 November 1975 AO 24-75:in Jul 1975,design Analysis Not Done for Addition of Breaker & New Security Sys Load to safety-related 480 Volt Bus 2A.Caused by Administrative Control Failure.Circuit Design Analysis Requested to Justify Circuit Configuration ML20151C2041975-07-23023 July 1975 AO 17-75:on 750718,daily Discharge Canal Water Sample Not Taken & Analyzed Per Tech Specs Requirements.Caused by Personnel Failure to Perform Routine Duty.Technicians Informed of Deficiency.Adherence to Requirements Stressed ML20151C2301975-05-30030 May 1975 AO 15-75:on 750530,fuel Pool & Reactor Drain Valve CV/4027 Found Leaking During Isolation Valve Integrity Testing.Cause Being Investigated ML20151C2281975-05-28028 May 1975 AO 14-75:on 750526,excessive Leakage Noted During Monthly Containment Ventilation Supply Valve Leak Test.Cause Not Known.Test Terminated & Reported to Plant Mgt.Investigation in Progress ML20151C2251975-05-24024 May 1975 AO 13-75:on 750523,locknut on MO/7053 Found Loose.Caused by Design Deficiency.Locknut Tightened & Staked to Drive Sleeve.Investigation in Progress to Determine Other Corrective Measures ML20151C2201975-05-23023 May 1975 AO 12-75:on 750521,excessive Operator Freeplay Noted Due to Loose Locknut on Core Spray Valve Operator.Caused by Design Deficiency.Locking Nut Tightened & Staked W/Pin Punch to Drive Sleeve.Investigation in Progress ML20151C2151975-05-21021 May 1975 AO 11-75:on 750520,during Calibr of Vacuum Interlock Switch PS/RE15B,setpoint Found Above Tech Specs Limits.Caused by Misapplication.Wide Range Switch Used W/Setpoint at Extreme Low End.Switch Restrictive Reset Characteristic Is Limiting 1975-07-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C3031999-09-28028 September 1999 Annual Rept of Facility Changes,Tests & Experiments ML20199A6621999-01-0505 January 1999 Special Rept:On 981230,hi Range Noble Gas Monitor Was Inoperable for Greater than Seven Days.Cause Unknown. Preplanned Alternate Method of Monitoring Appropriate Parameters within 72 H Was Established ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML20198K6611998-12-24024 December 1998 Safety Evaluation Supporting Amend 120 to License DPR-6 ML20154E0371998-09-30030 September 1998 Safety Evaluation Accepting Request for Exemption from Certain Portions of 10CFR50.47(b) & App E to 10CFR50 to Allow Brpnp to Discontinue Offsite EP Activities & Reduce Scope of Onsite EP as Result of Permanently Shutdown ML20154E0581998-09-30030 September 1998 Safety Evaluation Accepting Licensee Request from Exemption from Certain Portions of 10CFR50.47(b) ML20198K0091998-09-18018 September 1998 SER Accepting Licensee Request for Exemption from Certain 10CFR50 Requirements for Emergency Planning for Big Rock Nuclear Plant ML20217N2131998-04-24024 April 1998 Brpnp Zircaloy Oxidation Analysis ML20216K0011998-04-16016 April 1998 Safety Evaluation Approving Licensee Request Re Plant Training Program for Certified Fuel Handlers ML20217H4641998-03-26026 March 1998 Rev 2 to Post Shutdown Decommissioning Activities Rept (Psdar) ML20202G1941998-02-12012 February 1998 Rev 7 to Updated Final Hazards Summary Rept for Big Rock Point Plant ML20154A7591997-10-0808 October 1997 10CFR50.59 Annual Rept of Facility Changes,Tests & Experiments, Since 971008 ML20216E4731997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Big Rock Point Plant ML20141J8731997-08-14014 August 1997 Safety Evaluation Supporting Amend 119 to License DPR-6 ML20210H5601997-07-31031 July 1997 Monthly Operating Rept for July 1997 for Brpnp ML20148T4901997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Big Rock Point Nuclear Plant ML20148N9251997-06-0606 June 1997 Rev 18 to CPC-2A, Quality Program Description for Operational Nuclear Plants ML20140C8981997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Big Rock Nuclear Power Plant ML20138J0121997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Big Rock Point ML20137X0161997-04-18018 April 1997 Safety Evaluation Accepting Changes to Rev 17 of CPC Quality Program Description for Operational NPPs (CPC-2A) ML20137J9381997-04-0202 April 1997 Safety Evaluation Supporting Amend 118 to License DPR-6 ML20137P0391997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Big Rock Point Nuclear Plant ML20135F2361997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Big Rock Nuclear Plant ML20148N9181997-02-0101 February 1997 Rev 17 to CPC-2A, Quality Program Description for Operational Nuclear Plants ML20134H3691997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Big Rock Point Nuclear Plant ML20137F2101996-12-31031 December 1996 1996 Annual Financial Rept CMS Energy ML20133C5421996-12-31031 December 1996 Monthly Operating Rept for Dec 1996 for Big Rock Point Nuclear Plant ML20135E5101996-11-30030 November 1996 Monthly Operating Rept for Nov 1996 for Big Rock Point Nuclear Plant ML20134H3381996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for Big Rock Point Nuclear Plant ML20211N1561996-10-0808 October 1996 Annual Rept of Facility Changes,Tests & Experiments, Consisting of Mods & Miscellaneous Changes Performed Since 961008 ML20128F9821996-09-30030 September 1996 Monthly Operating Rept for Sept 1996 for Big Rock Point Nuclear Plant ML20059E8321993-12-31031 December 1993 Monthly Operating Rept for Dec 1993 for Big Rock Point Nuclear Plant ML20058K0931993-11-30030 November 1993 Monthly Operating Rept for Nov 1993 for Big Rock Point Nuclear Plant ML20058E8961993-11-29029 November 1993 1993 ISI Rept 3-1 Big Rock Point Plant, for 930626-0905 ML20058F3441993-11-22022 November 1993 Safety Evaluation Concurring W/Contractor Findings Presented in Technical Evaluation Rept EGG-RTAP-10816, Evaluation of Utility Responses to Suppl 1 to NRC Bulletin 90-01;Big Rock Point ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20058A1601993-11-15015 November 1993 Safety Evaluation Supporting Amend 112 to License DPR-6 ML20059J4531993-10-31031 October 1993 Monthly Operating Rept for Oct 1993 for Big Rock Point Nuclear Plant ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20057E1981993-10-0505 October 1993 Safety Evaluation Supporting Amend 111 to License DPR-6 ML20057E8341993-09-30030 September 1993 Monthly Operating Rept for Sept 1993 for Big Rock Point Nuclear Plant ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20056G9171993-08-31031 August 1993 Monthly Operating Rept for Aug 1993 for Big Rock Point Nuclear Plant ML20056E1661993-08-16016 August 1993 Safety Evaluation Supporting Amend 110 to License DPR-6 ML18058B8821993-06-15015 June 1993 Rev 13 to Quality Program Description for Operational Nuclear Power Plants. ML20128P5501993-02-18018 February 1993 Section 2.5 of Big Rock Point Updated Final Hazards Summary Rept ML20128F3511993-01-31031 January 1993 Monthly Operating Rept for Jan 1993 for Big Rock Point Nuclear Plant ML20128C4341993-01-29029 January 1993 Forwards Rev 3 to Updated Final Hazards Summary Rept ML20058L8721992-12-31031 December 1992 1992 Annual Rept,Cpc ML20127K8941992-12-31031 December 1992 Revised Pages to Graybook Rept for Dec 1992 for Big Rock Point Nuclear Plant 1999-09-28
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i :s ij THIS REPORT IS SU3MITTED TO CONFIRM THE TELEPHot E REPORT TO D 1:ILEY j j OF YOUR OFFICE ON MAY 20, 1975.
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- 3. FACILITY - BIG ROCK POINT PLANT, CHARLEVOIX hd L.u Q'lg 4. IDEt:TIFICATION OF OCCURRE! CE - PRESSURE SWITCH DRITT ON CON-DENSER L0V' VACUUM. SCRAM.It1TERLOCK.':
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- 6. DESCRIPTION OF OCCURRENCE - DURIN3 ROUTIt:E CALIBRATIO!! 0F VACULG INTEHLOCK SVITCH PS/REISB, THE SETPOINT VAS FOUND TO BE 362 PSIG.
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fw 1 THf. TECHNICAL UPECV TMCATXON CIALL5 f@W LLC 55 TMW 3$$ I'SId - tNEF ij 6.1.3 /E/ FOOTN')TE
- TECHNICAL SPECIFICATIONS. THE C ITCH Ht.S BEEN hJ; READJUSTED TO OPERAiE AT 339 PSIG.
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@j,) i 7. DESIGNATION OF APPARENT CAUSE OF OCCURRENCE - PRESCL' rte SUITCH I DRIFT- BOTH It: CREASE A'ND DECREASE HAS BEE EXPERIENCED IN THE PAET p
-l VITH THESE SUITCHES. THE SASIC PROBLEM IS A MISAPPLICATICN IN THAT
$,-Nl! A VIDE RANGE SWITCH HAS BEEN USED WITH A SETPOINT AT THE E".TRE::F. LCU !
d.> l END. ALSO, THE SYITCH CANNOT BE SET MUCH BELOV 353 PSIG BECAU3E OF
[G i THE RESTRICTIVE RESET CHARACTERISTIC OF THE VACUUM SCRAM S'JITCH l'HICH RESETS AT APPROXIMATELY 25" HG. THIS IS DIFFICULT TO ACHIEVE AT RE-ACTOR PRESSURE BELOV APPRO.XIMATELY 343 PSIG. l Cis l
dj, 8. ANALYSIS OF OCCURRENCE - THE OPERATING POINT OF 12 PSIG ADOVE THE u .:
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Gj! LIMIT OCCURRED ON ONE OF TVO SVITCHES IN THE PROTECTIVE SYSTEM CHAN-bf FEL AND THUS THE PROTECTIVF FUNCTION VAS OPERABLE. THE PROPOSED TECHNICAL SPECIFICATION OF MARCH 11, 1975 INDICATES OUR RECUEST TO r..
l45 RAISE THIS LIMIT TO SCC PSIG BASED ON SETTI!;GS THAT ARE ALLO ('ED IN (9
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ANOTHER SIMILAR BVR PLANT.
(# ! 9. CORRECTIVE ACTION - THE SWITCH VAS RESET TO OPERATE AT 339 PSIG
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l 10. FAJLURE DATA - REFERENCE SIMILAR PROBLEM VITH PS/RE15B IN A0-7-73 i REPORTED IN CUR LETTER OF MAY 8, 1973 AND A0-12 'I3 REPORTED IN OUR 4 j. i c[3 LETTER OF NOVE.'lBER 13, 1973, COMPONENT MANUFACTURER, BARKSDALE fiODEL 2 l 31 T A32 SS.
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