/03L-0 on 781006:oxygen Analyzer Valves CV-5065-12,CV-5065-16 & CV-5065-25 Appeared Inoperable,But Local Observation Showed Valves Working Properly.Caused by Switch Misalignment.Ler Inconsistent W/Ler in Cover LtrML20148F778 |
Person / Time |
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Site: |
Pilgrim |
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Issue date: |
11/02/1978 |
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From: |
Mathis C BOSTON EDISON CO. |
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To: |
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Shared Package |
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ML20148F764 |
List: |
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References |
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LER-78-046-03L-01, LER-78-46-3L-1, NUDOCS 7811090168 |
Download: ML20148F778 (2) |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20138Q5491997-02-0707 February 1997 LER 97-S02-00:on 970110,security Svcs Supervisor Received Improperly Mailed Safeguards Info.Caused by Personnel Error. Security Force Put on Heightened Awareness & Protected Area Patrol Frequency Increased ML20138Q5461997-02-0606 February 1997 LER 97-S01-00:on 970107,security Guard Found Loaded .380 Caliber Colt Automatic Pistol While Performing Routine Vehicle Check.Operator Did Not Intend to Bring Pistol on Site 05000293/LER-1993-0201993-08-23023 August 1993 LER 93-020-00:on 930726,plant Personnel Found Anticipated Transient Without Scram Div 1 Pressure Transmitters Valved Out of Svc.Caused by Lack of Procedural Clarity.Personnel Revised procedure.W/930823 Ltr 05000293/LER-1993-0191993-08-23023 August 1993 LER 93-019-00:on 930722,automatic Actuation of RHR Sys Portion of PCIS Occurred.Caused by Momentary Pressure Transient That Actuated Protective High Pressure Switches. Calibr performed.W/930823 Ltr 05000293/LER-1993-0181993-08-18018 August 1993 LER 93-018-00:on 930721,planned Shutdown Initiated Due to Unidentified Leakage of 3 Gpm.On 930722,planned Shutdown Became TS Required Shutdown When Insp Revealed Leakage to Be Rc Pressure Boundary Leakage.Leakage repaired.W/930818 Ltr 05000293/LER-1993-0161993-08-18018 August 1993 LER 93-016-00:on 930719,HPCI Sys Declared Inoperable.Caused by Depiction & Description of Field Common Connections on Panalarm Co Drawing.Field Common for Alarm Circuit re-established & tested.W/930818 Ltr 05000293/LER-1993-0171993-08-13013 August 1993 LER 93-017-00:on 930721,HPCI Sys Declared Inoperable Due to Turbine Steam Supply Valves Closure During Surveillance Testing.Hpci Logic Test Procedures Reviewed.Procedure 8.M.2-1.5.10 Being revised.W/930813 Ltr 05000293/LER-1993-0081993-05-0404 May 1993 LER 93-008-00:on 930409,determined Humidistats Not Tested from 880701 to 920123,in Excess of 42 Months.Caused by Personnel Failing to Perform Functional Test.Training Procedure implemented.W/930504 Ltr 05000293/LER-1981-015, Updated LER 81-015/03X-1:on 810417,during Surveillance Testing,Nozzle on 23-ft Level Cardox Sys Hose Reel Failed to Deliver Adequate Stream.Caused by Operator Error.Fire Brigade Training revised.W/840319 Ltr1984-03-19019 March 1984 Updated LER 81-015/03X-1:on 810417,during Surveillance Testing,Nozzle on 23-ft Level Cardox Sys Hose Reel Failed to Deliver Adequate Stream.Caused by Operator Error.Fire Brigade Training revised.W/840319 Ltr 05000293/LER-1980-041, Updated LER 80-041/03X-1:on 800724,isolation Valves 5065-17 & 5065-22 Declared Inoperable.Caused by Valve Limits Being Out of Adjustment.Valve Items Adjusted & Exercised to Provide Correct operation.W/840308 Ltr1984-03-0808 March 1984 Updated LER 80-041/03X-1:on 800724,isolation Valves 5065-17 & 5065-22 Declared Inoperable.Caused by Valve Limits Being Out of Adjustment.Valve Items Adjusted & Exercised to Provide Correct operation.W/840308 Ltr 05000293/LER-1981-009, Updated LER 81-009/03X-1:on 810319,inboard Isolation Valve Failed to Open & HPCI Sys Declared Inoperable.Caused by Incorrect Min Torque Switch Setting of Motor Operator & Thermal Binding.Torque Switch Set at Max value.W/8402081984-02-0808 February 1984 Updated LER 81-009/03X-1:on 810319,inboard Isolation Valve Failed to Open & HPCI Sys Declared Inoperable.Caused by Incorrect Min Torque Switch Setting of Motor Operator & Thermal Binding.Torque Switch Set at Max value.W/840208 Ltr 05000293/LER-1983-051, Updated LER 83-051/03X-1:on 830916,during steady-state Operations,Drywell Airborne Leak Detection Sys Found Inoperable.Caused by Low Flow Particulate Sys Traced to Water Clogged Filter & Leak in Sensing line.W/831031 Ltr1983-10-31031 October 1983 Updated LER 83-051/03X-1:on 830916,during steady-state Operations,Drywell Airborne Leak Detection Sys Found Inoperable.Caused by Low Flow Particulate Sys Traced to Water Clogged Filter & Leak in Sensing line.W/831031 Ltr 05000293/LER-1983-047, Telecopy LER 83-047/01X-0:on 830913,recirculation Pump low-low Water Trip Relay (16AK8A) Found Smoking.Power Deenergized.Failure of Relay Contacts Due to Coating of Smoke & Varnish.Relay Replaced1983-09-15015 September 1983 Telecopy LER 83-047/01X-0:on 830913,recirculation Pump low-low Water Trip Relay (16AK8A) Found Smoking.Power Deenergized.Failure of Relay Contacts Due to Coating of Smoke & Varnish.Relay Replaced 05000293/LER-1980-034, Updated LER 80-034/03X-1:on 800701 & 16,HPCI Turbine Discharge Line Snubber Found Severed & HPCI Declared Inoperable.Caused by Transient Hydrodynamic Shock During Startup & Shutdown of HPCI Turbine1983-07-0606 July 1983 Updated LER 80-034/03X-1:on 800701 & 16,HPCI Turbine Discharge Line Snubber Found Severed & HPCI Declared Inoperable.Caused by Transient Hydrodynamic Shock During Startup & Shutdown of HPCI Turbine 05000293/LER-1983-020, Telecopy LER 83-020/01X-0:on 830502,daily Surveillance Testing Per Tech Spec Section 4.11.D Not Performed.Caused by Failure to Revise Procedures & Inadvertent Removal of Sections from Tech Specs.Procedures Revised1983-05-0202 May 1983 Telecopy LER 83-020/01X-0:on 830502,daily Surveillance Testing Per Tech Spec Section 4.11.D Not Performed.Caused by Failure to Revise Procedures & Inadvertent Removal of Sections from Tech Specs.Procedures Revised 05000293/LER-1982-049, Telecopy LER 82-049/01X-0:on 821102,safety Valve a Found Set W/Nitrogen at Steam Relief Setting.Caused by Personnel Error.Properly Tested Spare Valve Installed.Personnel Admonished to Read & Follow Procedures Exactly1982-11-0202 November 1982 Telecopy LER 82-049/01X-0:on 821102,safety Valve a Found Set W/Nitrogen at Steam Relief Setting.Caused by Personnel Error.Properly Tested Spare Valve Installed.Personnel Admonished to Read & Follow Procedures Exactly 05000293/LER-1982-004, Telecopy Message of LER 82-004/01X-0:on 820222,primary Containment Isolation Valve Flanges Discovered W/Provision for Type B Llr Testing.Flanges Previously Type a Tested. Flanges Added to Llr Test Program1982-02-24024 February 1982 Telecopy Message of LER 82-004/01X-0:on 820222,primary Containment Isolation Valve Flanges Discovered W/Provision for Type B Llr Testing.Flanges Previously Type a Tested. Flanges Added to Llr Test Program ML20147C1671978-12-0808 December 1978 /03L-0 on 781115:during Test of Reactor Water Level,Level Switches L1S-263-57A&B Observed to Trip at Values Greater than Specified in Tech Specs.Caused by Minor Setpoint Drift ML20150D3841978-11-29029 November 1978 /01T-0 on 781116:during Repair of Fire Hydrant Facing Condenser Retube bldg,shut-off Valve Blew Off Line Causing Local Flooding & Removal of Fire Suppression from Svc.Cause Was Improper Reinstallation at Retube Bldg Constr ML20150D0691978-11-27027 November 1978 /03L-0 on 781028:SJAE Offgas Radiat Monitor Readings Were Low Caused by Shut Block Valve to FCV-118. Valve Was Opened.Proper Flow Rate Established.Valve Will Be Properly Identified in Future by Personnel ML20197D5081978-11-22022 November 1978 /01X-0 on 781030: of Operable Srm'S Was Reduced Below Minimum Req When SRM a Was Jumpered to Eliminate Problems W/Downscale Rod Block.Caused by Inadvertent Jumpering of Entire a SRM Trip Logic.Procedures Being Rev ML20197D0631978-11-14014 November 1978 /04T-0 on 781106:Yankee Environ Lab Indicated That 63pGi/kg of CO-60 Existed in Sample Mussel Meat.This Exceeds by 10 Times the Concentration Measured at Marshfield Control Station.Resulted from New Analysis Technique ML20148F7781978-11-0202 November 1978 /03L-0 on 781006:oxygen Analyzer Valves CV-5065-12,CV-5065-16 & CV-5065-25 Appeared Inoperable,But Local Observation Showed Valves Working Properly.Caused by Switch Misalignment.Ler Inconsistent W/Ler in Cover Ltr ML20197B9531978-11-0202 November 1978 /03L-0 on 781002:Position of Chief Radiol Engr Was Incorp Into PNPS Organization Which Assumed Responsibilities of Health Physics Organization.Caused by Efforts to Improve Quality of Health Physics Prog ML20147A7491978-09-0101 September 1978 /03L-0 on 780808:time Delay Relay Tdu 2E-K5B Settings Were Incorrect Due to Minor Setpoint Drift. Adjustments Were Made.(Encl to 7809180302 1997-02-07
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999 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
[Table view] |
Text
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05 DOCKI T NUMol H Ui b') LVE N T DATC 74 7b HLPOIIT DAll 00 EVf NT DEf"RIPTION AND PROBAul.L CONSEOULNCES l l 2 l l 0n 10-06-78, while investigating past problems with the oxygen analyzer valves, the l
,j3y l following valves appeared to be inoperable: CV-5065-12, 16 5 25 Valve CV-5065-12 had g, j j both open and closed indicating lights illuminated at all times: CV-5065-16andCV-5065-}5 had no indication in the closed position. Local observation verified that the valves
, g,l l were closing as required, therefore, the probable consequences of this event were minimal. A similar occurrence was reported in LER 78-024/03L-0 illl_J l !
B 9 00 SYSif M CAUSE CAUSE COMP.
CODE VALVE CODE SUBCODE COMPONENT CoDC %UECODE SUBCODE LJ2]
8 I si nl@ IE j@ l 9 to l@ lI lN lS lT lR lU l@ [SJQ [Z J g 11 12 13 10 19 20 Si OUENT I AL oCCUHHf NCE HEPO4T HE VISION g g n ,r g EVENT YE/ 4 HE PORT No. CODE TYPE N
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_ 21 22 23 24 2G 21 28 29 30 31 32 ACTION . f UTURE (FFECT SHUTDOWN ATTACW.'ENT NPnD-4 PHIME COMP. CO'.'PON E N T TAKEN /sC TIO N ONPLANT METHOD HOURS SUDMIT T E D FORMdUfL SUPPLif0 M ANUF ACT UR E H lElgl4Al@
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l [y lg 41 l N lg [_A g j M l 3 [0 l2 g 40 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h ,
i l O ] l The cause of this event was misalignment of the Lintit switch on CV-5065-12 and sticky l 3
]ill limit switches on CV-5065-16 & z5 CV-5065-12 was realigned, CV-5065-16 was cycled ;
,.;, g several times and freed, and CV-5065-25 limit switch was replaced. The limit switch for y ) CV-5065-16 has been scheduled for replacement. g i 141 l l B 9 80 F ACllliY METHOD OF STA1U5 % POWE H OTHE rl ST ATUS DISCOVL HY Dis. COVE HY QE SCit1PTION j ., ) l E j@ l 1 l 0 l 0 lg N.A. 4 lC Non routine 2nvest2 gat 2on l
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' 5 BOSTON EDISON COMPANY I PILGRIM NUCLEAR POWER STATION DOCKET No. 50-293 Attachment to LER 78-045/03L-0 1
Event Description l On October 6,1978, while investigating past problems with the oxygen analyzer valves, the following valves appeared to be inoperable:
CV-5065-12, 16 6 25. Valve CV-5065-12 haa both open and closed indicating lights illuminated at all times; CV-5065-16 and CV-5065-25 had no indication in the closed position.
Cause and Corrective Action The limit switch arm for valve CV-5065-12 was found to be misaligned and not nmking contact with the striker. The arm was realigned and proper operation of limit switches and valve positioning verified.
The open indication (rec. for valve CV-5065-16 appeared to be functioning properly as the light did extinguish af ter a few seconds when given a closed s ignal . The close indication (green), which should have illuminated when the valve was in the intermediate position and when fully closed, did not function at all. No apparent alignment problems were evident and after cycling the valve a couple of times, the close indication started illuminat;ng.
The valve was cycled several times and each time, proper operation of position indication was verified. The limit switches for this valve have been scheduled for replacement.
The symptoms associated with valve CV-5065-25 were the same as for valve CV-5065-16, however, cycling of the valve did not correct the situation.
Local observation of the valve indicated proper operation so a Maintenance Request was issued and the limit switch was replaced in kind.
.