/1T-0 on 780928:reactor Coolant Sys Pressure; Dropped.Rate in Decrease Reached 25 Psig Per Minute. Pressure Decrease Caused by Failed elec-to-air Signal ConverterML20062D320 |
Person / Time |
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Site: |
Point Beach |
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Issue date: |
09/29/1978 |
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From: |
Greenwood J WISCONSIN ELECTRIC POWER CO. |
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To: |
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References |
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LER-78-010-01T, LER-78-10-1T, NUDOCS 7811210349 |
Download: ML20062D320 (2) |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARNPL-97-0565, LER 97-S02-00:on 970815,perimeter Zones,Doors & Cameras Were Lost.Caused by Inadequate Compensatory Measures Taken for Failed Multiplexer.Repaired Mux for e-field Zone 81997-09-15015 September 1997 LER 97-S02-00:on 970815,perimeter Zones,Doors & Cameras Were Lost.Caused by Inadequate Compensatory Measures Taken for Failed Multiplexer.Repaired Mux for e-field Zone 8 NPL-97-0061, LER 97-S01-00:on 970204,compensatory Measures for Microwave Zones Had Not Been Implemented.Caused by Mgt Oversight of CAS & SAS Activities Was Inadequated.Addl Mgt Oversight of CAS & SAS Operations Has Been Implemented1997-03-0404 March 1997 LER 97-S01-00:on 970204,compensatory Measures for Microwave Zones Had Not Been Implemented.Caused by Mgt Oversight of CAS & SAS Activities Was Inadequated.Addl Mgt Oversight of CAS & SAS Operations Has Been Implemented 05000266/LER-1993-0071993-08-25025 August 1993 LER 93-007-00:on 930726,EDG Inadvertently Started and Station Battery Tripped Off Due to Undervoltage Signal. Caused by Blown Fuse as Result of Human Error During Calibr of 1A-06 Voltmeter.Fuse replaced.W/930825 Ltr 05000266/LER-1993-001, Revised LER 93-001-00:on 930107,all 4,160 Volt Degraded Grid Voltage Protection Channels Declared Inoperable Due to Discovery That Settings for Relays on Subj Channels Being Too Low.Plant Mods Will Be Made1993-02-16016 February 1993 Revised LER 93-001-00:on 930107,all 4,160 Volt Degraded Grid Voltage Protection Channels Declared Inoperable Due to Discovery That Settings for Relays on Subj Channels Being Too Low.Plant Mods Will Be Made 05000266/LER-1992-004, Corrected LER 92-004-00:on 920515,determined That One Svc Water Pump & One Containment Ventilation Fan Sequenced Onto EDG More Times than Listed in Fsar,Section 8.2.3.Caused by Time Delay Relay Out of Tolerence.Evaluation Under1992-07-0909 July 1992 Corrected LER 92-004-00:on 920515,determined That One Svc Water Pump & One Containment Ventilation Fan Sequenced Onto EDG More Times than Listed in Fsar,Section 8.2.3.Caused by Time Delay Relay Out of Tolerence.Evaluation Underway ML20077R5181991-08-14014 August 1991 LER 91-S01-00:on 910715,informed of Inadequate Preemployment Screening Process.Caused by Contractor Failure to Inform Util Employees Had Been Denied Access at Facility.Release & Authorization Form Revised 05000266/LER-1990-0061990-07-18018 July 1990 LER 90-006-00:on 900619,nuclear Instrumentation Turbine Runback Occurred.Caused by Spurious Signal Believed to Have Been Negative Spike.Voltage Spike Considered Spurious. W/900718 Ltr 05000266/LER-1985-002, Forwards LER 85-002-01 Re Details of Fuel Damage Found on Fuel Assembly H14,which Spent Last Cycle in Core Position D12.Rept Suppls Original Rept1986-05-19019 May 1986 Forwards LER 85-002-01 Re Details of Fuel Damage Found on Fuel Assembly H14,which Spent Last Cycle in Core Position D12.Rept Suppls Original Rept ML20203L0281986-04-25025 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 05000266/LER-1982-009, Telecopy Message of LER 82-009/01T-0:on 821030,tubes in Steam Generators a & B Found W/More than 40% Degradation.On 821025,insp Revealed 5 Wet or Dripping Explosive Plugs.No Cause Stated.Tubes Plugged1982-11-0101 November 1982 Telecopy Message of LER 82-009/01T-0:on 821030,tubes in Steam Generators a & B Found W/More than 40% Degradation.On 821025,insp Revealed 5 Wet or Dripping Explosive Plugs.No Cause Stated.Tubes Plugged 05000301/LER-1982-005, Updated LER 82-005/01T-1:on 820727,discovered 2 of 3 Level Instruments on C Boric Acid Storage Tank Powered from Common Source.Cause Not Determined Due to Poor Early Maint of Documents.Wiring Corrected1982-09-28028 September 1982 Updated LER 82-005/01T-1:on 820727,discovered 2 of 3 Level Instruments on C Boric Acid Storage Tank Powered from Common Source.Cause Not Determined Due to Poor Early Maint of Documents.Wiring Corrected ML20147C2781978-12-11011 December 1978 /03L on 781121:failure to Submit RO 50-366/78-55 W/In 30 Days.Caused by Deviation Rept 2-78-79 Not Received by Responsible Dept Head Nor Superintendent of Plant Engr Svcs.Personnel Were Reminded of Procedures ML20062E6581978-11-17017 November 1978 /01T-0 on 781106:turbine Runback Resulted from Safeguards Bus Tie Breaker Trip.Westinghouse Model CV-7 Undervoltage Relay on Tie Breaker Tripped Causing Breaker to Open.No Line Voltage Surges Detected ML20064E8621978-10-23023 October 1978 /01T-0 on 781009:snubber on Pressurizer Relief Line Was Found Inoperable.Grinnel Model HS-17,21/2 Inch X 5 Inch Bore & Stroke Snubber Failed for Undetermined Cause. Snubber Replaced & Surveillance Prog Expanded ML20062D4531978-10-13013 October 1978 /03L-0 on 780913:on 2 occasions,2 of 3 Charging Pumps Were isolated.2 3/4 Crosby Relief Valves Leaked Through Causing Temporary Loss of Charging Flow.Charging Pump Relief Valve Replaced & a Pump Returned to Svc ML20062D4671978-10-12012 October 1978 /01T-0 on 780928:reactor Coolant Sys Pressure Began Dropping at 25 Psi Per Minute;Pressurizer Spray Value 431B Found Partially Open Despite Shut Signal Due to 0 Set Point Drift Caused by Heat Degradation in Transducer ML20062D3201978-09-29029 September 1978 /1T-0 on 780928:reactor Coolant Sys Pressure; Dropped.Rate in Decrease Reached 25 Psig Per Minute. Pressure Decrease Caused by Failed elec-to-air Signal Converter 1997-09-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
[Table view] |
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September 29, 1978 Mr. James Kappler, Regional Director '
Office of Inspection and Enforcement, Region III 4 U. S. Nuclear Regulatory Commission 799 Roosevelt Road ,
Glen Ellyn, Illinois 60137 Dear Mr. Keppler L
LICENSEE EVENT REPORT No. 78-010/0lT-0 24 HOUR WRITTEN NOTIFICATION
~
_tPJ,,IT 2 REACTOR COOLANT _ SYSTEM PARTIAL DEPRESSURIZATION POINT BEACH NUCLEAR PLANT b
Licensee Names WIPBH2 License Number: 00-0000-00 License Type: 41111 Docket Number: 50-301 !
Report Source: L Event Date: 09-28-78
{
Event
Description:
At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> en 09-28-78 it was noted that I reactor coolant system pressure had dropped 35 psig from its I normal operating pressure of 2235 psig during the previous 30 minutes. The pressure continued to drop slowly until 1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br /> j when pressure then began dropping at a rate of 25 psig per min-t ute. At 1302 hours0.0151 days <br />0.362 hours <br />0.00215 weeks <br />4.95411e-4 months <br /> a ramp decrease in power level of 54 per ,
minute was manually initiated to prevent an automatic trip via the overtemperature AT trip instrumentation (DNB protection). j
?
Since there were no indications of increasing radioactivity levels !
in containment throughout this entire period, it was postulated .
that a problem with the pressurizar spray valve controls existed i and an operator entered the containment to investigate this possi- !
bility. At 1316 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.00738e-4 months <br /> pressurizer spray valve 531B (air-operated, i fail air to shut) was>found partially open despite a manual full l shut signal. Air pressure to the valve operator was relieved and ,
the valve closed. Reactor coolant system pressure began recovery immediately. The problem was traced to a failed electrical-to-air ;
signal (I/p) converter. The converter was replaced at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />; the spray valve then being returned to service. i
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i Mr. James Kappler 2 September 29, 1978 ,
Unit 2 LER 78-010/01T-0 i i
k The lowest pressurs recorded was 1965 psig. Limiting Condition for Operation, Technical Specification 15.3.1.A.4.A.2 states that pressure may not drop below 2220 psia when nor:nal operating pressure is 2250 psia. Lowest power level reached during the manual ramp down was approximately 165 MWe.
' A Manager's Supervisory Staff review of the situation was conducted immediately following the event and return to full power was [
approved after a complato discuasion. The unit achieved full power at 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br />, 09-28-78. j-A gross beta-gamma analysis of the reactor coolant system on 09-29-78 h
(
disclosed no advarse effects upon fuel integrity following the -l transient nor was there any indication of steam generator primary-to-second ey leakage.
This event is reportable in accordance with Technical Specification '
15.6.9.2.A.2. $
g f/4 AAwd J Greenwood Tetephone: 414/7s5-2321 't i
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