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| {{#Wiki_filter:* NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150--0104 (4195)* EXPIRES 4130/98 PER RESPONSE TO COllPL Y wmi THIS llANDATORY INFORllATION LICENSEE EVENT REPORT (LER) COU£CT10N REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED | | {{#Wiki_filter:NRC FORM 366 (4195)* |
| -* -INTO THE LICENStHG PROCESS NID FED BACK TO INDUSTRY. | | U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150--0104 EXPIRES 4130/98 ESTIMATED~ PER RESPONSE TO COllPL Y wmi THIS llANDATORY INFORllATION COU£CT10N REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED |
| FORWARD COllllEHTS REGARDING BURDEN ESTIMATE TO THE INFORllATION NID.RECOROS -GEllEHT BRANCH (T-<I F33), U.S. "-'Ct.EAR REGUIATORY COlllllSSION. | | -* - LICENSEE EVENT REPORT (LER) INTO THE LICENStHG PROCESS NID FED BACK TO INDUSTRY. FORWARD COllllEHTS REGARDING BURDEN ESTIMATE TO THE INFORllATION NID.RECOROS -GEllEHT BRANCH (T-<I F33), U.S. "-'Ct.EAR REGUIATORY COlllllSSION. WASHINGTON, DC 2QS5S. |
| WASHINGTON, DC 2QS5S. (See reverse for required number of digits/characters for each block) 0001, NID TO THE REOUC'TION PROJECT (315G-010C, OFFICE OF -aEllEHT NID BUOGET, WASHINGTON, DC 20503 FACILITY NAME (1) DOCKET NUMBER (2) Page (3) PALISADES NL)CLEAR PLANT. 05000255 1of4 TITLE(4) LICENSEE EVENT REPORT 96-006-01 | | 0001, NID TO THE PAPERWOR~ REOUC'TION PROJECT (315G-010C, OFFICE OF (See reverse for required number of digits/characters for each block) -aEllEHT NID BUOGET, WASHINGTON, DC 20503 FACILITY NAME (1) DOCKET NUMBER (2) Page (3) |
| -REACTOR POWER LICENSE LIMIT-VOLUNTARY SUPPLEMENTAL REPORT . EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) .
| | PALISADES NL)CLEAR PLANT. 05000255 1of4 TITLE(4) |
| * OTHER FACILITIES INVOLVED (8). MONTH DAY YEAR YEAR , . SEQUENTIAL REVISION MONTH DAY .YEAR FACILITY NAME DOCKET NUMBER _ NUMBER NUMBER 05000 02 07 96 96. 006 01 08 *02 96 FACILITY NAME DOCKET NUMBER --05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check one or more) (11) MODE (9) N 20.2201(b) 20.2203(a)(2)(v) 50.73(a)(2)(1) | | LICENSEE EVENT REPORT 96-006 REACTOR POWER LICENSE LIMIT- VOLUNTARY SUPPLEMENTAL REPORT EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) . |
| : 50. 73(a)(2)(iii)
| | * OTHER FACILITIES INVOLVED (8). |
| I POWER I 100 I 20.2203(a)(1) 20.2203(a)(3)(1) 50.73(a)(2)(ii) . 73(a)(2)(x) | | YEAR , . SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR MONTH DAY .YEAR |
| LEVEL (10) 20.2203(a)(2)(1) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) x Voluntary Report 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v)
| | _ NUMBER NUMBER 05000 02 07 96 96. - 006 - 01 08 *02 96 FACILITY NAME DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check one or more) (11) |
| Specify in Abstract below or 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(viil in NRC Form 366A LICENSEE CONTACT FOR THIS LER (12) " NAME TELEPHONE NUMBER (Include Area Code) Philip D Flenner, Licensing Engineer (616) 764-2544 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE -SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) MONTH* DAY YEAR I YES . x I NO EXPECTED If yes COMPLETE EXPECTED COMPLETION DATE SUBMISSION DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) On February 7, 1996, a planned delithiation procedure was performed in accordance with plant procedures. | | MODE (9) 20.2201(b) 20.2203(a)(2)(v) 50.73(a)(2)(1) 50. 73(a)(2)(iii) |
| As expected, the power level increased during the. procedure. | | N I POWER LEVEL (10) I I 100 20.2203(a)(1) 20.2203(a)(2)(1) 20.2203(a)(3)(1) 20.2203(a)(3)(ii) 50.73(a)(2)(ii) . |
| The power level was controlled and monitored in compliance with the existing procedures and resulted in an indicated plant power in excess of 100% of licensed power for nine consecutive hours. That indication and the initial investigation of the associated measurement uncertainties led to the event being reported as LER 96-006 on March 11, 1996 as a condition possibly outside of the design basis and in violation of a license condition of 100% power level. LER 96-006 also indicated that our investigation was continuing. | | 50.73(a)(2)(iii) x 50~ 73(a)(2)(x) 73.71 l~~~~l:'f, il~:J;,,f ''11!!~1 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) Voluntary Report 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v) Specify in Abstract below or 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(viil in NRC Form 366A LICENSEE CONTACT FOR THIS LER (12) |
| Subsequent-tests and analyses have shown that Palisades did not exceed the established design basis and did not exceed 100% power during the period .in Accordingly, this LER is being reclassified as a voluntary report. question. | | NAME TELEPHONE NUMBER (Include Area Code) |
| 9608140240 960802 PDR ADOCK 05000255 S PDR : I I I I 1* I I . , I 1-. | | Philip D Flenner, Licensing Engineer (616) 764-2544 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | CAUSE - SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) MONTH* DAY YEAR I YES . |
| | If yes COMPLETE EXPECTED COMPLETION DATE x I NO EXPECTED SUBMISSION DATE (15) |
| | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) |
| | On February 7, 1996, a planned delithiation procedure was performed in accordance with plant I procedures. As expected, the power level increased during the. procedure. The power level was I controlled and monitored in compliance with the existing procedures and resulted in an indicated I plant power in excess of 100% of licensed power for nine consecutive hours. That indication and I the initial investigation of the associated measurement uncertainties led to the event being 1* |
| | reported as LER 96-006 on March 11, 1996 as a condition possibly outside of the design basis I and in violation of a license condition of 100% power level. LER 96-006 also indicated that our I investigation was continuing. Subsequent-tests and analyses have shown that Palisades did not exceed the established design basis and did not exceed 100% power during the period .in I question. Accordingly, this LER is being reclassified as a voluntary report. 1- . |
| | 9608140240 960802 PDR ADOCK 05000255 S PDR |
| | |
| I ' | | I ' |
| * NRC FORM 366a 4195 .. U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME 11 l DOCKET12\
| | NRC FORM 366a 4195 .. |
| PALISADES.NUCLEAR PLANT 05000255 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) EVENT DESCRIPTION . ' . ?f' LER NUMBER 16) YEAR I SEQUENTIAL REVISION NUMBER NUMBER 96 006 01 *1,( | | * LICENSEE EVENT REPORT (LER) |
| * PAGE 13\ 2 OF 4 On February 7, 1996, a planned delithiation procedure was performed in accordance with plant procedures.
| | U.S. NUCLEAR REGULATORY COMMISSION TEXT CONTINUATION I |
| As expected, the power level increased during the procedure. | | FACILITY NAME 11 l DOCKET12\ LER NUMBER 16) |
| The power level was controlled and monitored in compliance with the existing procedures and resulted in the indicated plant power in excess of 100% of licensed power for nine consecutive hours. That indieation and the initial investigation of the involved measurement uncertainties led to the event being reported as LER 96-006 on March 11 , 1996 as a condition possibly outside of the design basis and in violation of a license condition of 100% power level. The Palisades operating license authorizes reactor operation " ... at steady state power levels not in excess of 2530 Megawatts thermal (100 percent rated power) ... " Palisades' procedures considered this steady state limit to be met if reactor power averaged over 24 hours was below 2530 megawatts | | * PAGE 13\ |
| .. Minor excursions a,bove 100 percent power were viewed as acceptable as long as peak power did not exceed 101 percent and 24-hour average power was less than 2530 megawatts. | | YEAR SEQUENTIAL REVISION NUMBER NUMBER PALISADES.NUCLEAR PLANT 05000255 2 OF 4 96 006 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| The slow power rise caused by dissolved boron removal during delithiation was viewe.d as a transient condition not subject to the steady state limit specified in the license. During a later review of level records, questions were raised about whether 24-hour averaging or 8-hour averaging should be used to assure license compliance, and whether measurement were adequately cqnsidered in the. procedure limit on peak power. Subsequent tests and analyses have shown that. Palisades did not exceed the establisheq basis and did not exceed 100% power during the period in question. | | EVENT DESCRIPTION J |
| Accordingly, this LER is being re<?lassified as a voluntary report. " EVENT ANALYSIS Two separate actions were taken during the investigation of this event. These actions were: 1. The calorimetric uncertainty analysis was redone to more accurately reflect the calorimetric uncertainty. | | . *1,( |
| This analysis was rigorously reviewed by CPCo and an . outside contractor with significant experience in uncertainty analyses. | | ~; ' |
| *2. An ultrasonic flow measurement (UFM) of the feedwater flow, originally scheduled for late 1996 or early 1997, was performed on May 21-22, 1996, to assess the plant *thermal performance. | | . ?f' I |
| The UFM provided an accurate measurement of feedwater flow independent of the installed feedwater venturies. | | On February 7, 1996, a planned delithiation procedure was performed in accordance with plant I procedures. As expected, the power level increased during the procedure. The power level was I controlled and monitored in compliance with the existing procedures and resulted in the indicated I plant power in excess of 100% of licensed power for nine consecutive hours. That indieation and the initial investigation of the involved measurement uncertainties led to the event being reported as LER 96-006 on March 11 , 1996 as a condition possibly outside of the design basis and in violation of a license condition of 100% power level. |
| J I I I I
| | The Palisades operating license authorizes reactor operation "... at steady state power levels not in excess of 2530 Megawatts thermal (100 percent rated power) ... " Palisades' procedures considered this steady state limit to be met if reactor power averaged over 24 hours was below 2530 megawatts .. Minor excursions a,bove 100 percent power were viewed as acceptable as long as peak power did not exceed 101 percent and th~ 24-hour average power was less than 2530 megawatts. The slow power rise caused by dissolved boron removal during delithiation was viewe.d as a transient condition not subject to the steady state limit specified in the license. During a later review of po~er level records, questions were raised about whether 24-hour averaging or 8-hour averaging should be used to assure license compliance, and whether measurement uncert~inties were adequately cqnsidered in the. procedure limit on peak power. |
| * NRC FORM 366a U.S. NUCLEAR REGULATORY COMMISSION
| | Subsequent tests and analyses have shown that. Palisades did not exceed the establisheq d~sign basis and did not exceed 100% power during the period in question. Accordingly, this LER is being re<?lassified as a voluntary report. |
| ,.* 4195. FACILITY NAME 11l PALISADES NUCLEAR PLANT LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKETt21 LERNUMBER 51 05000255 YEAR I SEQUENTIAL REVISION NUMBER NUMBER 96 006 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PAGE 13\ 3 OF 4 The final results from the uncertainty analysis show the actual calorimetric uncertainty to be 1.01 %. When the new calorimetric uncertainty of 1.01 % is added to the maximum power level recorded (100.41%),*the resulting value is within the Palisades Design Basis value of 102%. It is therefore concluded that Palisades did not exceed the design basis throughout this event. The results of the UFM revealed thafactual power (measured using the UFM results) was 2.2% less than measured power based on the feedwater venturies.
| | EVENT ANALYSIS Two separate actions were taken during the investigation of this event. These actions were: |
| The conservative bias is due primarily toa conservative initial venturi calibration and to venturi fouling. The stated uncertainty for the UFM device is comparable to the stated uncertainty for the feedwater venturies. | | : 1. The calorimetric uncertainty analysis was redone to more accurately reflect the calorimetric uncertainty. This analysis was rigorously reviewed by CPCo and an |
| The UFM device is considered to be more accurate due to rigorous testing by the vendor and the device's independence from fouling. Using the ultrasonic flow results, the maximum power level achieved during the event was 98.2%. It has therefore been concluded that Palisades did not exceed 100% licensed po\\'.er throughout the event. SAFETY SIGNiFICANCE Since the investigation showed that the power level remained below 100% and within the design basis at all times, there is no safety significance to this event. CAUSE OF THE EVENT ' . The ro_ot cause for the event as initially reported. | | . outside contractor with significant experience in uncertainty analyses. |
| was that the *procedural guidance for the operators regarding compliance with licensed steady-stateJeactor core power levels was not sufficiently conservative.* | | *2. An ultrasonic flow measurement (UFM) of the feedwater flow, originally scheduled for late 1996 or early 1997, was performed on May 21-22, 1996, to assess the plant |
| * * | | *thermal performance. The UFM provided an accurate measurement of feedwater flow independent of the installed feedwater venturies. |
| | |
| | NRC FORM 366a 4195. |
| | * LICENSEE EVENT REPORT (LER) |
| | U.S. NUCLEAR REGULATORY COMMISSION TEXT CONTINUATION I |
| | FACILITY NAME 11l DOCKETt21 LERNUMBER 51 PAGE 13\ |
| | YEAR SEQUENTIAL REVISION NUMBER NUMBER PALISADES NUCLEAR PLANT 05000255 3 OF 4 96 006 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| | The final results from the uncertainty analysis show the actual calorimetric uncertainty to be 1.01 %. When the new calorimetric uncertainty of 1.01 % is added to the maximum power level recorded (100.41%),*the resulting value is within the Palisades Design Basis value of 102%. It is therefore concluded that Palisades did not exceed the design basis throughout this event. |
| | The results of the UFM revealed thafactual power (measured using the UFM results) was 2.2% |
| | less than measured power based on the feedwater venturies. The conservative bias is due primarily toa conservative initial venturi calibration and to venturi fouling. The stated uncertainty for the UFM device is comparable to the stated uncertainty for the feedwater venturies. The UFM device is considered to be more accurate due to rigorous testing by the vendor and the device's independence from fouling. Using the ultrasonic flow results, the maximum power level achieved during the event was 98.2%. It has therefore been concluded that Palisades did not exceed 100% |
| | licensed po\\'.er throughout the event. |
| | SAFETY SIGNiFICANCE Since the investigation showed that the power level remained below 100% and within the design basis at all times, there is no safety significance to this event. |
| | CAUSE OF THE EVENT The ro_ot cause for the event as initially reported. was that the *procedural guidance for the operators regarding compliance with licensed steady-stateJeactor core power levels was not sufficiently conservative.* * * |
| * CORRECTIVE ACTIONS The following corrective actions were accomplished: | | * CORRECTIVE ACTIONS The following corrective actions were accomplished: |
| Upon realizing that there was some possibility that the design analyses limit could be exceeded due to measurement uncertainties, immediate direction was given to the Operators to avoid exceeding the power limit of 2530 Mwt and to take immediate action to reduce the power below 2530 Mwt if it was exceeded. | | Upon realizing that there was some possibility that the design analyses limit could be exceeded due to measurement uncertainties, immediate direction was given to the Operators to avoid exceeding the power limit of 2530 Mwt and to take immediate action to reduce the power below 2530 Mwt if it was exceeded. |
| Operating procedures have been revised to treat the 2530 Mwt limit as an absolute limit which would require immediate corrective action if it is exceeded. | | Operating procedures have been revised to treat the 2530 Mwt limit as an absolute limit which would require immediate corrective action if it is exceeded. |
| NRC FORM 366a 4/95 . U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME 11 l PALISADES NUCLEAR PLANT LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET/2\ | | |
| LER NUMBER 6l 05000255 YEAR I SEQUENTIAL . NUMBER 96 006 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) REVISION NUMBER 01 PAGE 131 40F 4 | | NRC FORM 366a U.S. NUCLEAR REGULATORY COMMISSION 4/95 . |
| * The calorimetric uncertainty analysis was revi.sed to more accurately known *
| | LICENSEE EVENT REPORT (LER) |
| * uncertainties.
| | TEXT CONTINUATION FACILITY NAME 11 l DOCKET/2\ LER NUMBER 6l PAGE 131 YEAR I SEQUENTIAL . |
| The ,analysis revealed that Palisades remained within the established design | | NUMBER REVISION NUMBER PALISADES NUCLEAR PLANT 05000255 40F 4 |
| * basis at all times. A flow test using UFM 1 originally scheduled for late 1996 or early 1997, was performed May 21-22, 1996. The results of the flow measurement revealed that the installed flow venturies . have a conservative bias. This resulted in the indicated reactor power reading higher than . the actual power. The measurement indicated that 100% power was not exceeded | | * 96 006 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| * throughout the event. PREVIOUS EVENTS No previous events have found.}} | | The calorimetric uncertainty analysis was revi.sed to more accurately refl~ct known ** |
| | uncertainties. The ,analysis revealed that Palisades remained within the established design |
| | * basis at all times. |
| | A flow test using UFM 1 originally scheduled for late 1996 or early 1997, was performed May 21-22, 1996. The results of the flow measurement revealed that the installed flow venturies . |
| | have a conservative bias. This resulted in the indicated reactor power reading higher than |
| | . the actual power. The measurement indicated that 100% power was not exceeded |
| | * throughout the event. |
| | PREVIOUS EVENTS No previous events have b~en found.}} |
LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit| ML18065A860 |
| Person / Time |
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| Site: |
Palisades  |
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| Issue date: |
08/02/1996 |
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| From: |
Flenner P
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
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| To: |
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| Shared Package |
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| ML18065A859 |
List: |
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| References |
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| LER-96-006, LER-96-6, NUDOCS 9608140240 |
| Download: ML18065A860 (4) |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18065B1151997-12-0909 December 1997
LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability
ML18067A7751997-11-11011 November 1997
LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved
ML18067A7581997-10-30030 October 1997
LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation
ML18067A7461997-10-23023 October 1997
LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure.
ML18067A7191997-10-10010 October 1997
LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed
ML18067A6951997-09-24024 September 1997
LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts
ML18067A5651997-06-0303 June 1997
LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested
ML18067A5461997-05-12012 May 1997
LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities
ML18067A4431997-03-24024 March 1997
LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS
ML18067A4391997-03-21021 March 1997
LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired
ML18067A4401997-03-21021 March 1997
LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr
ML18066A8931997-02-21021 February 1997
LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr
ML18066A8751997-02-0505 February 1997
LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr
ML18066A8041996-12-23023 December 1996
LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment
ML18066A7831996-12-16016 December 1996
LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced
ML18065A9951996-10-0404 October 1996
LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg
ML18065A9171996-09-0909 September 1996
LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr
ML18065A8961996-08-29029 August 1996
LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments
ML18065A8811996-08-20020 August 1996
LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced
ML18065A8741996-08-16016 August 1996
LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected
ML18065A8651996-08-12012 August 1996
LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr
ML18065A8601996-08-0202 August 1996
LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit
ML18065A8321996-08-0101 August 1996
LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board
ML18065A7691996-06-12012 June 1996
LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr
ML18065A6901996-05-0101 May 1996
LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr
ML18065A6681996-04-22022 April 1996
LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr
ML18065A5721996-03-11011 March 1996
LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded
ML18065A5261996-03-0101 March 1996
LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr
ML18065A5111996-02-19019 February 1996
LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr
ML18065A5061996-02-19019 February 1996
LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts
ML18065A5021996-02-15015 February 1996
LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr
ML18065A4581996-01-31031 January 1996
LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr
ML18065A4421996-01-19019 January 1996
LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr
ML18065A4041996-01-15015 January 1996
LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr
ML18065A3291995-12-0404 December 1995
LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr
ML18065A2361995-11-0202 November 1995
LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr
ML18065A2051995-10-20020 October 1995
LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised
ML18065A0841995-09-18018 September 1995
LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr
ML18065A0681995-09-14014 September 1995
LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line
ML18065A0651995-09-0808 September 1995
LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment
ML18064A8781995-08-28028 August 1995
LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage
ML18064A8831995-08-21021 August 1995
LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr
1999-09-02
[Table view]
Category:RO)
MONTHYEARML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18065B1151997-12-0909 December 1997
LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability
ML18067A7751997-11-11011 November 1997
LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved
ML18067A7581997-10-30030 October 1997
LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation
ML18067A7461997-10-23023 October 1997
LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure.
ML18067A7191997-10-10010 October 1997
LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed
ML18067A6951997-09-24024 September 1997
LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts
ML18067A5651997-06-0303 June 1997
LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested
ML18067A5461997-05-12012 May 1997
LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities
ML18067A4431997-03-24024 March 1997
LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS
ML18067A4391997-03-21021 March 1997
LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired
ML18067A4401997-03-21021 March 1997
LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr
ML18066A8931997-02-21021 February 1997
LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr
ML18066A8751997-02-0505 February 1997
LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr
ML18066A8041996-12-23023 December 1996
LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment
ML18066A7831996-12-16016 December 1996
LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced
ML18065A9951996-10-0404 October 1996
LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg
ML18065A9171996-09-0909 September 1996
LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr
ML18065A8961996-08-29029 August 1996
LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments
ML18065A8811996-08-20020 August 1996
LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced
ML18065A8741996-08-16016 August 1996
LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected
ML18065A8651996-08-12012 August 1996
LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr
ML18065A8601996-08-0202 August 1996
LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit
ML18065A8321996-08-0101 August 1996
LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board
ML18065A7691996-06-12012 June 1996
LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr
ML18065A6901996-05-0101 May 1996
LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr
ML18065A6681996-04-22022 April 1996
LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr
ML18065A5721996-03-11011 March 1996
LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded
ML18065A5261996-03-0101 March 1996
LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr
ML18065A5111996-02-19019 February 1996
LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr
ML18065A5061996-02-19019 February 1996
LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts
ML18065A5021996-02-15015 February 1996
LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr
ML18065A4581996-01-31031 January 1996
LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr
ML18065A4421996-01-19019 January 1996
LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr
ML18065A4041996-01-15015 January 1996
LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr
ML18065A3291995-12-0404 December 1995
LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr
ML18065A2361995-11-0202 November 1995
LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr
ML18065A2051995-10-20020 October 1995
LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised
ML18065A0841995-09-18018 September 1995
LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr
ML18065A0681995-09-14014 September 1995
LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line
ML18065A0651995-09-0808 September 1995
LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment
ML18064A8781995-08-28028 August 1995
LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage
ML18064A8831995-08-21021 August 1995
LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr
1999-09-02
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999
Rev 5 to Palisades Nuclear Plant Colr.
ML18066A6761999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant
ML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6351999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant
ML18066A6771999-08-31031 August 1999
Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A6061999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr
ML18066A5201999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr
ML18066A4841999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr
ML18066A6371999-04-30030 April 1999
Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant
ML18068A5941999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr
ML18066A4161999-04-0101 April 1999
Rev 4 to COLR, for Palisades Nuclear Plant
ML18066A4501999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr
ML18066A4671999-03-31031 March 1999
Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant.
ML18068A5351999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr
ML18066A3931999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML20206F6131998-12-31031 December 1998
1998 Consumers Energy Co Annual Rept. with
ML18066A3651998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr
ML18066A3421998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr
ML18066A3301998-11-11011 November 1998
Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used
ML18068A4921998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A3181998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant
ML18066A2901998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr
ML18066A3191998-08-31031 August 1998
Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML20237E0301998-07-31031 July 1998
ISI Rept 3-3
ML18066A2701998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr
ML18066A2311998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Palisades Nuclear Plant
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A3061998-06-18018 June 1998
SG Tube Inservice Insp.
ML20249C4951998-06-17017 June 1998
Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18066A1711998-06-0101 June 1998
Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46
ML18066A1741998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr
ML18066A2321998-05-31031 May 1998
Revised MOR for May 1998 for Palisades Nuclear Plant
ML18068A4701998-05-31031 May 1998
Annual Rept of Changes in ECCS Models Per 10CFR50.46.
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18066A2331998-04-30030 April 1998
Revised MOR for Apr 1998 for Palisades Nuclear Plant
ML18068A3461998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr
ML18066A3411998-04-22022 April 1998
Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events.
ML18065B2071998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr
ML20217C2741998-03-31031 March 1998
Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts
ML18066A2341998-03-31031 March 1998
Revised MOR for Mar 1998 for Palisades Nuclear Plant
ML18068A3041998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr
ML18066A2351998-02-28028 February 1998
Revised MOR for Feb 1998 for Palisades Nuclear Plant
ML18065B1641998-02-0505 February 1998
Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance.
ML18067A8211998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr
1999-09-30
[Table view] |
Text
NRC FORM 366 (4195)*
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150--0104 EXPIRES 4130/98 ESTIMATED~ PER RESPONSE TO COllPL Y wmi THIS llANDATORY INFORllATION COU£CT10N REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED
-* - LICENSEE EVENT REPORT (LER) INTO THE LICENStHG PROCESS NID FED BACK TO INDUSTRY. FORWARD COllllEHTS REGARDING BURDEN ESTIMATE TO THE INFORllATION NID.RECOROS -GEllEHT BRANCH (T-<I F33), U.S. "-'Ct.EAR REGUIATORY COlllllSSION. WASHINGTON, DC 2QS5S.
0001, NID TO THE PAPERWOR~ REOUC'TION PROJECT (315G-010C, OFFICE OF (See reverse for required number of digits/characters for each block) -aEllEHT NID BUOGET, WASHINGTON, DC 20503 FACILITY NAME (1) DOCKET NUMBER (2) Page (3)
PALISADES NL)CLEAR PLANT. 05000255 1of4 TITLE(4)
LICENSEE EVENT REPORT 96-006 REACTOR POWER LICENSE LIMIT- VOLUNTARY SUPPLEMENTAL REPORT EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) .
- OTHER FACILITIES INVOLVED (8).
YEAR , . SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR MONTH DAY .YEAR
_ NUMBER NUMBER 05000 02 07 96 96. - 006 - 01 08 *02 96 FACILITY NAME DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check one or more) (11)
MODE (9) 20.2201(b) 20.2203(a)(2)(v) 50.73(a)(2)(1) 50. 73(a)(2)(iii)
N I POWER LEVEL (10) I I 100 20.2203(a)(1) 20.2203(a)(2)(1) 20.2203(a)(3)(1) 20.2203(a)(3)(ii) 50.73(a)(2)(ii) .
50.73(a)(2)(iii) x 50~ 73(a)(2)(x) 73.71 l~~~~l:'f, il~:J;,,f 11!!~1 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) Voluntary Report 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v) Specify in Abstract below or 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(viil in NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Philip D Flenner, Licensing Engineer (616) 764-2544 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE - SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) MONTH* DAY YEAR I YES .
If yes COMPLETE EXPECTED COMPLETION DATE x I NO EXPECTED SUBMISSION DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On February 7, 1996, a planned delithiation procedure was performed in accordance with plant I procedures. As expected, the power level increased during the. procedure. The power level was I controlled and monitored in compliance with the existing procedures and resulted in an indicated I plant power in excess of 100% of licensed power for nine consecutive hours. That indication and I the initial investigation of the associated measurement uncertainties led to the event being 1*
reported as LER 96-006 on March 11, 1996 as a condition possibly outside of the design basis I and in violation of a license condition of 100% power level. LER 96-006 also indicated that our I investigation was continuing. Subsequent-tests and analyses have shown that Palisades did not exceed the established design basis and did not exceed 100% power during the period .in I question. Accordingly, this LER is being reclassified as a voluntary report. 1- .
9608140240 960802 PDR ADOCK 05000255 S PDR
I '
NRC FORM 366a 4195 ..
- LICENSEE EVENT REPORT (LER)
U.S. NUCLEAR REGULATORY COMMISSION TEXT CONTINUATION I
FACILITY NAME 11 l DOCKET12\ LER NUMBER 16)
YEAR SEQUENTIAL REVISION NUMBER NUMBER PALISADES.NUCLEAR PLANT 05000255 2 OF 4 96 006 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
EVENT DESCRIPTION J
. *1,(
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. ?f' I
On February 7, 1996, a planned delithiation procedure was performed in accordance with plant I procedures. As expected, the power level increased during the procedure. The power level was I controlled and monitored in compliance with the existing procedures and resulted in the indicated I plant power in excess of 100% of licensed power for nine consecutive hours. That indieation and the initial investigation of the involved measurement uncertainties led to the event being reported as LER 96-006 on March 11 , 1996 as a condition possibly outside of the design basis and in violation of a license condition of 100% power level.
The Palisades operating license authorizes reactor operation "... at steady state power levels not in excess of 2530 Megawatts thermal (100 percent rated power) ... " Palisades' procedures considered this steady state limit to be met if reactor power averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was below 2530 megawatts .. Minor excursions a,bove 100 percent power were viewed as acceptable as long as peak power did not exceed 101 percent and th~ 24-hour average power was less than 2530 megawatts. The slow power rise caused by dissolved boron removal during delithiation was viewe.d as a transient condition not subject to the steady state limit specified in the license. During a later review of po~er level records, questions were raised about whether 24-hour averaging or 8-hour averaging should be used to assure license compliance, and whether measurement uncert~inties were adequately cqnsidered in the. procedure limit on peak power.
Subsequent tests and analyses have shown that. Palisades did not exceed the establisheq d~sign basis and did not exceed 100% power during the period in question. Accordingly, this LER is being re<?lassified as a voluntary report.
EVENT ANALYSIS Two separate actions were taken during the investigation of this event. These actions were:
- 1. The calorimetric uncertainty analysis was redone to more accurately reflect the calorimetric uncertainty. This analysis was rigorously reviewed by CPCo and an
. outside contractor with significant experience in uncertainty analyses.
- 2. An ultrasonic flow measurement (UFM) of the feedwater flow, originally scheduled for late 1996 or early 1997, was performed on May 21-22, 1996, to assess the plant
- thermal performance. The UFM provided an accurate measurement of feedwater flow independent of the installed feedwater venturies.
NRC FORM 366a 4195.
- LICENSEE EVENT REPORT (LER)
U.S. NUCLEAR REGULATORY COMMISSION TEXT CONTINUATION I
FACILITY NAME 11l DOCKETt21 LERNUMBER 51 PAGE 13\
YEAR SEQUENTIAL REVISION NUMBER NUMBER PALISADES NUCLEAR PLANT 05000255 3 OF 4 96 006 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
The final results from the uncertainty analysis show the actual calorimetric uncertainty to be 1.01 %. When the new calorimetric uncertainty of 1.01 % is added to the maximum power level recorded (100.41%),*the resulting value is within the Palisades Design Basis value of 102%. It is therefore concluded that Palisades did not exceed the design basis throughout this event.
The results of the UFM revealed thafactual power (measured using the UFM results) was 2.2%
less than measured power based on the feedwater venturies. The conservative bias is due primarily toa conservative initial venturi calibration and to venturi fouling. The stated uncertainty for the UFM device is comparable to the stated uncertainty for the feedwater venturies. The UFM device is considered to be more accurate due to rigorous testing by the vendor and the device's independence from fouling. Using the ultrasonic flow results, the maximum power level achieved during the event was 98.2%. It has therefore been concluded that Palisades did not exceed 100%
licensed po\\'.er throughout the event.
SAFETY SIGNiFICANCE Since the investigation showed that the power level remained below 100% and within the design basis at all times, there is no safety significance to this event.
CAUSE OF THE EVENT The ro_ot cause for the event as initially reported. was that the *procedural guidance for the operators regarding compliance with licensed steady-stateJeactor core power levels was not sufficiently conservative.* * *
- CORRECTIVE ACTIONS The following corrective actions were accomplished:
Upon realizing that there was some possibility that the design analyses limit could be exceeded due to measurement uncertainties, immediate direction was given to the Operators to avoid exceeding the power limit of 2530 Mwt and to take immediate action to reduce the power below 2530 Mwt if it was exceeded.
Operating procedures have been revised to treat the 2530 Mwt limit as an absolute limit which would require immediate corrective action if it is exceeded.
NRC FORM 366a U.S. NUCLEAR REGULATORY COMMISSION 4/95 .
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME 11 l DOCKET/2\ LER NUMBER 6l PAGE 131 YEAR I SEQUENTIAL .
NUMBER REVISION NUMBER PALISADES NUCLEAR PLANT 05000255 40F 4
- 96 006 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
The calorimetric uncertainty analysis was revi.sed to more accurately refl~ct known **
uncertainties. The ,analysis revealed that Palisades remained within the established design
A flow test using UFM 1 originally scheduled for late 1996 or early 1997, was performed May 21-22, 1996. The results of the flow measurement revealed that the installed flow venturies .
have a conservative bias. This resulted in the indicated reactor power reading higher than
. the actual power. The measurement indicated that 100% power was not exceeded
PREVIOUS EVENTS No previous events have b~en found.