ML19257C656
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| ML19257C656 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 01/24/1980 |
| From: | Mcloughlin M BOSTON EDISON CO. |
| To: | |
| References | |
| NUDOCS 8001290555 | |
| Download: ML19257C656 (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 MESSAGE '
To: l'3-337-5324 Telephone Number
- Date/ Time: 1/24/ 0 / 1500 f
To: Director, Region I .
From: Pilgrim Nuclcar Power Station Office of Inspection and Enforcement RFD #1 Rocky 11111 Road U. S. Nuclear Regulatory Commission Plymouth, MA 02360 631 Park Avenue King of Prussia, PA 19406 Subj ect: PROMPT REPORTABLE OCCURRENCE Docket Number 50-293; License DPR-35
' Assigned LER Number 80-002/01X-0 Event
Description:
An investigati n .in-itiated following review of IE Information Notice No. 79-32 has revealed a cable separation inadequacy. Several 125V DC ADS supply cables are routed in cable trays that contain HPCI control cables. This item is reportable via PNPS T.S. Section 6.9.1.1.
Cause and Corrective Actioni I= mediate action is being taken to resolve this problem prior to s cartuo following our etfrrent Refuel 4 Outage.
Facility Status: 0 c) Routine Startup % Thermal MW g) Shutdown d) Routine Shutdown h) Refueling X e) Steady State f) Load Changing 1) Other j) Not Applicaple t written follow-up report vill be sent within two weeks.
GC person notified Mr. David-Kehoe Prepared by Mr. M. Thomas McLoughlin
- n 182f 128 v... .
%0 tail (2) copies to:
- Director #
Office of Management Information and Program Control 100i800' '
U. S. Nuclear Regulatory Commission ,
Washington, D.C. 20555 .
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