(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20199A6621999-01-0505 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 ML20058H6851990-11-14014 November 1990 Special Rept:On 901024,high-range Noble Gas Monitor Inoperable for More than 72 H ML20207L8191988-10-12012 October 1988 Special Rept:On 880913,high Range Noble Gas Effluent Monitor Detector Failed Due to Water Intrusion Into Detector Well. on 880915,spare Detector Installed & Tested,Resulting in Discovery That Source Check Circuit Not Operating Properly ML20151U8361988-08-11011 August 1988 Ro:On 880715,discovered That Fission Chamber Containing 4 Uci U-235 & 0.05 Uci U-238 Missing.Accountability Program Upgraded to More Rigorously Incorporate Small Quantities of non-fuel SNM ML20197E7171988-06-0303 June 1988 Special Rept:On 880426,diesel Fire Pump Selector Switch Placed to Off Position Defeating Auto Start Feature of Pump for More than 7 Days.Temporary Change to Battery Test Procedure Restored Battery Svcs Prior to Operability ML20055A6771982-05-26026 May 1982 Telecopy Message of Ro:On 820525,multiple Minor Through Wall Tube Leaks Discovered in B Heating & Cooling Hx,Initially Reported 820526.HX Valved Out of Svc Pending Completion of Repairs ML20054F7681981-06-15015 June 1981 Telecopy Message of Ro:On 820611,electrical Fire in turbine- Generator Exciter Forced Shutdown of Reactor.No Radiological Release or Injuries to Employees.Fire Controlled in 1/2-h. Extensive Damage to Exciter Brushers ML20151C1901976-01-20020 January 1976 RO P-1-76:on 760119,inadequate Design Pressure Ratings Found on Relief Switches DPS-9051 & 9052,transmitter PT-173 & Reactor Protection Containment Pressure Switches PS-664,665, 666 & 667.Caused by Inadequate Design Specs ML20126E3471966-08-0909 August 1966 Ro:On 660808,after Reactor Trip Due to Lightning,Turbine Generator Did Not Trip & Continued to Carry Facility Power from Residual Steam in Primary Sys,Reducing Reactor Pressure.Caused by Bypass Valve Malfunction 1999-01-05
[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
[Table view] |
Text
7
\ Consumers f> . Power
^"
POWERING MKHIGAN'S PROGRES5 General offices: 1945 West Parnall Road, Jackson, MI 49201 * (517) 788-0550 June 3. 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
TECHNICAL SPECIFICATION 3.7.11.1 SPECIAL REPORT - FIRE SUPPRESSION WATER SYSTEM Consumers Power Company's Big Rock Point Plant Technical Specification 3.7.11.1 requires that the Fire Suppression Water System to operate at all times with automatic starting of the pumps on decaying fire system pressure.
Action statement "a" to this technical specification require a Special Report be submitted to the NRC if during a time when the Fire Suppression Water System is inoperable, the inoperable equipment is not returned to service within seven days. Pursuant to this requirement, a Special Report is attached explaining the incident which required the auto-start feature of the fire pumps to be defeated for greater than 7 days, fp # J Brian D Johnson )
Staff Licensing Engineer l CC Administrator, Region III, NRC NRC Resident Inspector - Big Rock Point Attachment
/ 't OC0688-0033-NL02 \
I 8606090275 880603 PDR ADOCK 05000155 S DCD
- c. -
BIG ROCK POINT PLANT SPECIAL REPORT PER TECHNICAL SPECIFICATION 3.7.11.1 l
Description of Occurrence On 4/26/88, the Diesel Fire Pump selector switch was placed to the "off" position which defeats the auto-start feature of the pump. This was required to prevent the diesel from running continuously during performance of the UPS Battery Service Test required by Technical Specification 11.4.5.3.A.1.(h). I Follo"ing performance of the Service Test a procedure required the battery to be fully recharged prior to returning it to service. On 5/3/d8, the battery was still in the process of beir.g recharged when the seven (7) day time period associated with the Diasel Fire Pump lapsed. On 5/4/88 a temporary change to the Battery Test procedure was approved which permitted rectoring the Battery to service prior to the cells reaching fully charged status. This action allowed the selector switch on the Diesel to be returned to the "auto" positicn thus restoring the auto-start feature required by Technical l Specification 3.7.11.1.c. Following unit testing, the Diesel Fire Pump was l declared operable on 5/5/88 at 0937 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.565285e-4 months <br />. l Safety Assessment During this time period the plant was in a Refueling Outage with all fuel l removed from the core. Additionally, the Electric Fire Pump was inservice and '
capable of auto-start on decaying system pressure.
Although the Diesel Fire Pump was not capable of auto-start during the period, l
should the need have arisen, the pump could have been manually started by '
returning the switch to the "auto" position. With this manual start capability the diesel pump was available as a hack-up to the electric providing a reasonable degree of redundancy for this mode of operation.
Actions to Prevent Recurrence The UPS Battery Service Test prccedure will be permanently revised to allow returning the Diesel Fire Pump start circuit to service prior to completion of cell recharge. This should reduce the time period the auto-start feature is out of service to less than seven (7) days, during Refueliog Outages when the Technical Specification Battery Surveillance tests are required to be performed.
OC0688-0033-NLO2