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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points ML20147B1511978-09-27027 September 1978 /03L-0 on 780831:during Monthly Specific Gravity Readings on Reactor Depressurization Sys,Battery A,Cell 12 Read 1.193 Below Limit of 1.200 Specified in Tech Specs. Cause Unknown & Cell Was Replaced.(Encl to 7810060072) ML20147B1461978-09-27027 September 1978 /03L-0 on 780829:during Tests of Automatic Containment Isolation Valves,Valve CV/4027 Exhibited Excessive Leakage.Valve & Piping Flushed & Leakage Test Repeated Satisfactorily.(Encl to 7810060072) ML20204B0911978-09-15015 September 1978 /03L-0 on 780819:Failure of Check Valve Providing Containment Integrity in 2 Demineralized Water Line Contributed to Containment of Plant Demineralized Water Sys Check Valve Repaired 780905 ML20147A8221978-09-12012 September 1978 /01L on 780904:During Test of Containment Ventilation Isolation Valves,Supply Valve CV/4097 Leaked in Excess of TS Criteria.Butterfly Valve Disc Seal Was Readjusted & Valved Returned to Svc. (Encl to 7809190156) 1986-04-25
[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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60 DOCKET NUMSER 69 74 EVENT DATI 76 REPORT DATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES O'o F5 m (Failure, between 7/26/78 and 8/19/78, of the check valve providing contain i O Iment integrity in the 2" demineralized water line to containment contrib- i g luted to radioactive contamination of the plant demineralized water system. i (T m ITwenty-five gallons of this water was removed from the plant by employees. l 0 l Containment integrity was established on 8/21/78 and evaluation on 8/23/78 i 1017l trevealed that no undue health hazard exists for any employees or the pub- l 10181 111c .
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, lReportability is based on T/S 6.9.2.b.(2). Inadequate survey per 10CFR20.-1 g 1201 resulted in unmonitored removal of water from the site and revised ad- I m iministrative i e n controla are being implemented to prevent recurrence. I STA % POWER OTHER$TATV5 Y ISCO DISCOVERY DESCRIPTION 32 y [E,,J@ l 0 l 8 I Ol@l N/A l l B l@l Trending of Sample Resu1Cs l
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Attachment to LER 032-011-0 Consumers Power Co '
Big Rock Point Plant Docket 050-155 Investigation of abnormally high radioactive materials levels in Lake Michigan water samples between 7/26/78 and 8/19/78 led to the discovery that the samples contained radioactive impurities caused by contamina-tion of the plant demineralized water supply. Demineralized water is used to rinse the sampling hardware. Evaluation on 8/21/78 established that the 2" containment isolation check valve in the demineralized water supply line to containment was defective and that backflow from the fuel pool system was the source of contamination in the demineralized water system.
On 8/21/78, redundant valve CV/4105 was closed to isolate the source of contamination and it was verified leak-tight on 8/25/78 following uri-fication on 8/25/78 that the 2" check valve was defective. Demineraliz-ed water taps and lines in the turbine buildina; were closed and/or caution tagged on 8/21/78 and 8/22/78. All on-site employees were informed of the problem on 8/21/78 and a survey was initiated to determine if unmonitored demineralized water had been used by anyone or removed from the plant.
l The survey revealed that about 25 gallons of water had been removed from )
the site in several containers. Of the fifteen gallons of water retriev- ;
ed, the highest activity was in the order of 100 120 in one five-gallon l container. Evaluation of each unretrievable use determined that no human l consumption occurred and no undue hazard existed for any empicyee or the public.
The exact mechanism for cross-contamination is not known but the 2" check valve in the demineralized water supply to the containment has been repaired and tested and the design of the valve will be reviewed to determine if reliability can be improved. In addition, manual valves VSFP-20 and VSFP-27 (one in each of the two fuel pool system connections to the demineralized water system) have been placed under lock control to preclude misoperation.
The removal of contaminated water from the plant is the result of inadequate survey practices. Periodic testing of the demineralized water is now being conducted to detect contamination and radiological clearance practice for removal of material from the site is being reviewed for possible improvements.