ML19254C727
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| ML19254C727 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/10/1979 |
| From: | Mathis C BOSTON EDISON CO. |
| To: | |
| References | |
| NUDOCS 7910170268 | |
| Download: ML19254C727 (1) | |
Similar Documents at Pilgrim | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20042E2261990-04-0909 April 1990
[Table view]Special Rept:On 900227,fire Protection Alarm Reporting Sys Inoperable for More than 14 Days.Compensatory Fire Watches Instituted in Affected Areas & Failure & Malfunction Rept 90-44 Written to Document Problem ML19325E9021989-11-0606 November 1989 Special Rept:On 890929,fire Water Supply Sys Storage Tanks Declared Inoperable.Caused by Drained Storage Tank. Fwst (T-107A) Refilled & Declared Operable on 891007 ML20052E1801982-04-27027 April 1982 RO 82-011/01X-0:on 820427,review of Water Level Anomaly, Determined That Facility Entered Limiting Condition for Operation W/O Insertion of Control Rods.Special Order 82-04 Will Be Issued 820428 to Prevent Recurrence ML20050D5851982-04-0101 April 1982 Ro 82-008/01x-0:on 820331,HPCI Sys Declared Inoperable Due to Failure of HPCI Injection Valve Mo 2301-8 to Go Full Open During Performance of Surveillance Test 8.I.13. Cause Not Stated.Priority a Maint Request Issued ML20042A4581982-03-0909 March 1982 Telecopy RO 82-006/01X-0:on 820309,HPCI Stop Valve Main Disc Flange Which Should Be Attached to Main Disc by Four Cap Screws Found W/Three Cap Screws Broken.Cause Not Stated. Engineering Support Requested ML20039E0771981-12-15015 December 1981 RO 81-1:on 811208,util Received Analysis Rept from Yankee Atomic Environ Lab Indicating Potentially Reportable Concentration of Co-60 in Irish Moss Sample from Indicator Station.Calculated Doses Not Considered Significant ML20050C2121981-03-25025 March 1981 RO 82-07/01X-0:on 810325,HPCI,reactor Core Isolation Cooling & Reactor Water Cleanup Pipe Excess Flow Isolation Setpoints Set Unconservatively.Caused by Exclusion of plant-specific Parameters from Original Calculation ML20049A3361980-11-14014 November 1980 RO 80-084/01X-0:on 801113,during Repairs to D Msn Discovered Water Leaking from 2 Inch Vessel Drain Line Which Connects to Rwcv Sys.Caused by Defective 2 Inch Pipe Coupling Weld. Leak Isolated & Coupling Rewelded ML19340B1611980-10-15015 October 1980 RO 80-072/01X-0:on 801014,during Steady State Operation,Mgt Review Revealed That Reactor Protection Sys Trip Level Setting Was Miscalibrated to Nonconservative Level.Caused by Calculation Error.Monitors Were Immediately Recalibrated ML19340B1621980-10-14014 October 1980 RO 80-070/01X-0:on 801010,during Steady State operation,480 Volt Breaker B204 Tripped Twice within 10 Minutes, de-energizing 480 Volt Bus B14.Cause Unknown.Bus B14 Was Immediately Returned to Svc by Closing Breaker B204 ML19351D6751980-10-0303 October 1980 RO 80-067/01X-0:on 801002,NRC Was Notified That Analytical Reanalysis of RHR Sys B Indicated That as-built Configuration Would Not Remain Functional During Sse.Caused by Design Error.Seismic Anchor Is Being Modified ML19343A4191980-09-11011 September 1980 RO 80-050/01X-0:on 800907,during Surveillance Testing,Diesel Generator Removed from Svc When RBCCW Pump P202D Found Inoperable.Caused by Ambiguous Tech Specs.Tech Specs Will Be Revised to Clarify Limiting Condition of Operation ML19338C4281980-08-0707 August 1980 RO 80-036/01X-0:on 800807,found Hourly Fire Check of Auxiliary Offgas Bldg Was Not Performed on Continuous Basis After 800707.Hourly Fire Check Reinitiated,Surveillance Testing Completed & Sys Returned to Svc ML19330C5121980-07-17017 July 1980 RO 80-29/01X-0:on 800701,during Surveillance Testing to Verify Operability of Oxygen Analyzer Isolation Valves, SV-5065-23 Failed to Meet Acceptance Criteria for Closing Time,Impacting on Operability of Panel C-19 ML19309G6631980-03-0808 March 1980 RO 80-008/01X-0:on 800308,two Irradiated Fuel Assemblies Relocated in Spent Fuel Pool,W/Diesel Generators Inoperable & Secondary Containment Not Intact.Caused by Lack of Knowledge Re Core Drilling for Mods.Fuel Movements Stopped ML19260D4021980-02-0101 February 1980 LER 80-004/012-0:during Visual Examination of Core Spray Sparger,Seven Linear Indications Were Recorded.Cause Unstated.Analysis Initiated ML19257C6561980-01-24024 January 1980 RO 80-002/01X-0:during Investigation Following Review of IE Info Notice 79-32,several 125-volt Dc Automatic Depressurization Sys Supply Cables Found Routed in Cable Trays Containing HPCI Control Cables.Problem Being Resolved ML19257C6471980-01-23023 January 1980 RO 80-001/01X-0:fire Hazards Rept Indicated That Fire in Raceways of Facility Cannot Be Tolerated Because Safe Shutdown Would Be Jeopardized.Cause Unstated.Fire Protection Measures Proposed or Being Completed ML19262B5691979-12-24024 December 1979 RO-79-048 on 791224:backup Battery Charger,In Use Due to Main Battery Charger 791223 Failure,Tripped & Could Not Be Reset.Cause Under Investigation.Spare Battery Charger Will Be in Svc by 791224 ML19270H6271979-12-20020 December 1979 Ro:On 791211,while Transferring Fuel Assembly LTL-656,crane Lifted Assembly Out of Spent Fuel Pool.Caused by Failure to Monitor Hook While Withdrawing from Pool.Assembly Returned to Proper Position ML19322C0241979-12-17017 December 1979 RO 79-01/OR:on 791217,while Lowering New Fuel Assembly Into Fuel Pool,Rice Hook Holding Assembly Failed,Resulting in Assembly Falling Onto Spent Fuel.Cause Not Yet Determined. Investigation Underway Re Recovery of Assembly ML19254C7271979-10-10010 October 1979 Ro:On 791009,Bechtel Notified Util That Reanalysis of Reactor Bldg Component Cooling Water Sys as-built Configuration Indicated Sys Would Not Remain Functional During Sse.Caused by Design Error.Mods Underway ML19209B6971979-10-0202 October 1979 RO 79-036/01X-0:on 791001,util Was Informed That Portion of Loop Piping Does Not Meet SSE Criteria.Caused by Failure to Include Pipe Flange Weights in Design Calculations ML19249B5731979-08-28028 August 1979 RO 79-032/01X-0 on 790828:during Evaluation Performed Per IE Bulletin 79-01,dry Well Sump Containment Isolation Valves AO-7011A & B & AO-7017A & B Were Found Unqualified for Svc. Caused by High Radiation Exposure to Solenoid Valve ML19249B5781979-08-28028 August 1979 RO 79-033/01X-0:on 790828,lightning Struck Station Switchyard,Causing Loss of Offsite Power & Reactor Scram. Offsite Power Restored & Reactor Startup Initiated ML19242C7761979-07-27027 July 1979 RO 79-027/01X-0 on 790727:lightning Struck Station Switchyard,Causing Loss of Offsite Power & Reactor Scram. HPCI Was Started for Injecting Water Into Vessel.Relief Valve 203-3A Will Be Replaced & Tested Prior to Restart 1990-04-09 Category:LER) MONTHYEARML20042E2261990-04-0909 April 1990
[Table view]Special Rept:On 900227,fire Protection Alarm Reporting Sys Inoperable for More than 14 Days.Compensatory Fire Watches Instituted in Affected Areas & Failure & Malfunction Rept 90-44 Written to Document Problem ML19325E9021989-11-0606 November 1989 Special Rept:On 890929,fire Water Supply Sys Storage Tanks Declared Inoperable.Caused by Drained Storage Tank. Fwst (T-107A) Refilled & Declared Operable on 891007 ML20052E1801982-04-27027 April 1982 RO 82-011/01X-0:on 820427,review of Water Level Anomaly, Determined That Facility Entered Limiting Condition for Operation W/O Insertion of Control Rods.Special Order 82-04 Will Be Issued 820428 to Prevent Recurrence ML20050D5851982-04-0101 April 1982 Ro 82-008/01x-0:on 820331,HPCI Sys Declared Inoperable Due to Failure of HPCI Injection Valve Mo 2301-8 to Go Full Open During Performance of Surveillance Test 8.I.13. Cause Not Stated.Priority a Maint Request Issued ML20042A4581982-03-0909 March 1982 Telecopy RO 82-006/01X-0:on 820309,HPCI Stop Valve Main Disc Flange Which Should Be Attached to Main Disc by Four Cap Screws Found W/Three Cap Screws Broken.Cause Not Stated. Engineering Support Requested ML20039E0771981-12-15015 December 1981 RO 81-1:on 811208,util Received Analysis Rept from Yankee Atomic Environ Lab Indicating Potentially Reportable Concentration of Co-60 in Irish Moss Sample from Indicator Station.Calculated Doses Not Considered Significant ML20050C2121981-03-25025 March 1981 RO 82-07/01X-0:on 810325,HPCI,reactor Core Isolation Cooling & Reactor Water Cleanup Pipe Excess Flow Isolation Setpoints Set Unconservatively.Caused by Exclusion of plant-specific Parameters from Original Calculation ML20049A3361980-11-14014 November 1980 RO 80-084/01X-0:on 801113,during Repairs to D Msn Discovered Water Leaking from 2 Inch Vessel Drain Line Which Connects to Rwcv Sys.Caused by Defective 2 Inch Pipe Coupling Weld. Leak Isolated & Coupling Rewelded ML19340B1611980-10-15015 October 1980 RO 80-072/01X-0:on 801014,during Steady State Operation,Mgt Review Revealed That Reactor Protection Sys Trip Level Setting Was Miscalibrated to Nonconservative Level.Caused by Calculation Error.Monitors Were Immediately Recalibrated ML19340B1621980-10-14014 October 1980 RO 80-070/01X-0:on 801010,during Steady State operation,480 Volt Breaker B204 Tripped Twice within 10 Minutes, de-energizing 480 Volt Bus B14.Cause Unknown.Bus B14 Was Immediately Returned to Svc by Closing Breaker B204 ML19351D6751980-10-0303 October 1980 RO 80-067/01X-0:on 801002,NRC Was Notified That Analytical Reanalysis of RHR Sys B Indicated That as-built Configuration Would Not Remain Functional During Sse.Caused by Design Error.Seismic Anchor Is Being Modified ML19343A4191980-09-11011 September 1980 RO 80-050/01X-0:on 800907,during Surveillance Testing,Diesel Generator Removed from Svc When RBCCW Pump P202D Found Inoperable.Caused by Ambiguous Tech Specs.Tech Specs Will Be Revised to Clarify Limiting Condition of Operation ML19338C4281980-08-0707 August 1980 RO 80-036/01X-0:on 800807,found Hourly Fire Check of Auxiliary Offgas Bldg Was Not Performed on Continuous Basis After 800707.Hourly Fire Check Reinitiated,Surveillance Testing Completed & Sys Returned to Svc ML19330C5121980-07-17017 July 1980 RO 80-29/01X-0:on 800701,during Surveillance Testing to Verify Operability of Oxygen Analyzer Isolation Valves, SV-5065-23 Failed to Meet Acceptance Criteria for Closing Time,Impacting on Operability of Panel C-19 ML19309G6631980-03-0808 March 1980 RO 80-008/01X-0:on 800308,two Irradiated Fuel Assemblies Relocated in Spent Fuel Pool,W/Diesel Generators Inoperable & Secondary Containment Not Intact.Caused by Lack of Knowledge Re Core Drilling for Mods.Fuel Movements Stopped ML19260D4021980-02-0101 February 1980 LER 80-004/012-0:during Visual Examination of Core Spray Sparger,Seven Linear Indications Were Recorded.Cause Unstated.Analysis Initiated ML19257C6561980-01-24024 January 1980 RO 80-002/01X-0:during Investigation Following Review of IE Info Notice 79-32,several 125-volt Dc Automatic Depressurization Sys Supply Cables Found Routed in Cable Trays Containing HPCI Control Cables.Problem Being Resolved ML19257C6471980-01-23023 January 1980 RO 80-001/01X-0:fire Hazards Rept Indicated That Fire in Raceways of Facility Cannot Be Tolerated Because Safe Shutdown Would Be Jeopardized.Cause Unstated.Fire Protection Measures Proposed or Being Completed ML19262B5691979-12-24024 December 1979 RO-79-048 on 791224:backup Battery Charger,In Use Due to Main Battery Charger 791223 Failure,Tripped & Could Not Be Reset.Cause Under Investigation.Spare Battery Charger Will Be in Svc by 791224 ML19270H6271979-12-20020 December 1979 Ro:On 791211,while Transferring Fuel Assembly LTL-656,crane Lifted Assembly Out of Spent Fuel Pool.Caused by Failure to Monitor Hook While Withdrawing from Pool.Assembly Returned to Proper Position ML19322C0241979-12-17017 December 1979 RO 79-01/OR:on 791217,while Lowering New Fuel Assembly Into Fuel Pool,Rice Hook Holding Assembly Failed,Resulting in Assembly Falling Onto Spent Fuel.Cause Not Yet Determined. Investigation Underway Re Recovery of Assembly ML19254C7271979-10-10010 October 1979 Ro:On 791009,Bechtel Notified Util That Reanalysis of Reactor Bldg Component Cooling Water Sys as-built Configuration Indicated Sys Would Not Remain Functional During Sse.Caused by Design Error.Mods Underway ML19209B6971979-10-0202 October 1979 RO 79-036/01X-0:on 791001,util Was Informed That Portion of Loop Piping Does Not Meet SSE Criteria.Caused by Failure to Include Pipe Flange Weights in Design Calculations ML19249B5731979-08-28028 August 1979 RO 79-032/01X-0 on 790828:during Evaluation Performed Per IE Bulletin 79-01,dry Well Sump Containment Isolation Valves AO-7011A & B & AO-7017A & B Were Found Unqualified for Svc. Caused by High Radiation Exposure to Solenoid Valve ML19249B5781979-08-28028 August 1979 RO 79-033/01X-0:on 790828,lightning Struck Station Switchyard,Causing Loss of Offsite Power & Reactor Scram. Offsite Power Restored & Reactor Startup Initiated ML19242C7761979-07-27027 July 1979 RO 79-027/01X-0 on 790727:lightning Struck Station Switchyard,Causing Loss of Offsite Power & Reactor Scram. HPCI Was Started for Injecting Water Into Vessel.Relief Valve 203-3A Will Be Replaced & Tested Prior to Restart 1990-04-09 Category:TEXT-SAFETY REPORT MONTHYEARML20217E3021999-09-30030 September 1999
[Table view]Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20216F3511999-09-0808 September 1999 ISI Summary Rept for Refuel Outage 12 at Pnps ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209B9861999-06-23023 June 1999 Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13 ML20217N9061999-06-21021 June 1999 Rept of Changes,Tests & Experiments for Period of 970422-990621 ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207F9401999-03-0101 March 1999 Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station ML20207H5451999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With ML20197J3591998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With ML20195C9951998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With ML20154K0721998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20197C5011998-09-0404 September 1998 Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr ML20197C5471998-08-31031 August 1998 Rev 12C to Pilgrim Nuclear Power Station Colr ML20151W8231998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20237A9941998-07-31031 July 1998 Monthly Operating Rept for Pilgrim Nuclear Power Station ML20236U8201998-07-13013 July 1998 Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12) ML20236P0151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station ML20249A3741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr ML20247H2081998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20216G3911998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20248L2241998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station ML20202G5251998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station ML20203D6101997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station ML20202D5761997-11-0808 November 1997 1997 Evaluated Exercise BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20217H5621997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station ML20216J4131997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station ML20210J3321997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station 1999-09-08 |
Text
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BOSTON EDISON COMPANY TELECOPY MESSACE y,. 1-215-337 1000 Da e/ Time ~10/10/79 /
Telephone Number To: Director, region I From: Pilgrim Nuclear Power Station
. Of fice of Ir.spection and Enforcement RFD #1 Rocky Hill Road U. S. Nuclear Regulatory Commission Plymouth, MA 02360 631 Park Avenue '
King of Prussia, PA 19406 Subj ect: PROMPT REPORTAb)E OCCURRENCr.
Docket Number 50-293; License DPR-35 s
'Ar. signed LER Number
,o 79-039/'/r:QL .
Esent
Description:
At 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> on 10/9/79, Bechtel Corporation notified BECo that reanalysis of as built configuration of "B" RBCCW indicated that, analytically, thesystemwouldnotremainfunctionalduringSS$.
Cause and Corrective Action: This event resulted from a design error. Three supports are presently being modified to return the system to its original design criteria.
Facility Status: 80 % Thermal MW c) Routine Startup_, ,__ g) Shutdown d) Routine Shutdown h) Refueling e) Steady State x i) Other f) Load Changing j) St Applicaple
& written follow-up report will be sent within two weeks.
ERC person notified 'fr. Ralph Architzel Prepared by Mr. C. J. Mathis I157 J41 Nail (2) copies to: ,.
9s Director '
Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 7 910170 y}_ f, J -
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