/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 RevML20197D508 |
Person / Time |
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Site: |
Pilgrim |
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Issue date: |
11/22/1978 |
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From: |
BOSTON EDISON CO. |
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To: |
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Shared Package |
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ML20197D498 |
List: |
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References |
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LER-78-051-01X, LER-78-51-1X, NUDOCS 7811280335 |
Download: ML20197D508 (1) |
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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
,____-w/un---------- w coNTnOL QLOCK: l l l l l (PLEASE PillNT OR TYPE ALL REQUIRED INFO'IMATION)
@ l M l4 l P,) P l S l 1 jQl 0 l 0 l 0 l 0 l 0 l 0 l 0 l 0 l0 l0l0l@l4l1l1l1l1l@l l lg 8 9 LICLNSE E LOOL 14 lb LlCLNSE NUMUCH 2b , 26 LICENSL TYPE JQ 5 7 Ca r t,c'
>N'T Q 8
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DATE EVENT DESCRIPTION AND PROB ADLE CONSEQUENCES h
[TF1 I on 11/21/78, PNPS management was informed of OA audit 78-18, which identified an oc- l l currence that was contrary to limitin'g conditions for operations as specified in T.S. J
[ section 3.2.C.1 and Table 3.2.c. On 10/30/78 the number of operable SRMs was reduced l gl below the minimum required when SRM "A" was jiimpered to eliminate problems with the g f g downscale rod block. A reactor startup was in progress and SRM "D" was already by- ;
g[ passed because of a failed detector. g a l . l ,
B 9 60 SYSTEM CAUSE C A U';E COMP, VALyt CODE CODE SUBCODE CDMPoNENT CODE SUBCODE SUBCODE h 6 lI l A l@ l Al@ l C l@ l Il Nl S l T [R lU l@ W@ lg l@
9 10 ti 12 13 18 19 20 k;
EVEin YE AR .
SEQUE NTI AL HEPORT NO.
OCCURRENCE REFORT REVISION j-LER CODE TYPE No.
h ,rg/RO l7l8l 2% ??
l_l 23 l0 l5 l1 l 24 '
2G jfl 27 l0 l1 l 28 29 lXl 30 l_l 31 l0l 32 l
AKEN 'A TIO ONP T ET t ) HOURS SO T FO bVB. 5 P LlE MAN f ,. T RER lClQ[Hj@ j Zl@
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41 lN ]@ lN l@ l G j 0 l 8 l 0 l@ l 42 43 44 47 '
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h
! j o j l This event occurred when maintenance and repair personnel inadvertently jumpered out thel I I gl entire "A" SRM trip logic ins tead of only the downscale trip as approved by ORC. l l
l Station procedure 3.M.1-3 is being revised to require ORC approval of the specific l l location of jumper terminals to ensure that only those fanctions which are not required l l
f
,4 ; l are affected. l [
6 9 '
80 ST S % POWER OTHE R ST ATUS IS TY DISCoVEflY DESCillPTION
{ Qj@ l0l0l0l@l N.A.
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nELE ASED OF nELE ASE AMOUNT OF ACTIVITY LOCATION OF nELEASE I I l c,I I z l @ l Z i@l N.A. I I N.A. l l l 8 9 10 11 44 45 80 l l'ENSONNE L EXPOSURES - I NOVHE R TYPE DESCRIPTION i g l 0 l 0 l 0 l@l Z l@l N.A. l ,
FERSONNE L INJUI IES NUMDEH OESCitiPTION
{ l 609 l 0 l 0 l@l N.A. l l
11 12 00 LOSS or oft DAuAct 10 rACILITY 1YPE D E T.CulP 1 t ON
] lZl@l u o to N.A. l 80 ;
lNl t@l)LSCillPTiON inut N.A. l lllllllllllllj ,
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/ h710 0 A M>,T Charles J. Mathis so 09 vu ;.
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