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Category:Licensee Event Report (LER)
MONTHYEAR05000255/LER-2021-001, Atmospheric Steam Dump Valves Inoperable Due to Relay Failure2021-08-13013 August 2021 Atmospheric Steam Dump Valves Inoperable Due to Relay Failure ML18344A4142018-12-10010 December 2018 LER 1979-037-00 for Palisades Nuclear Plant, Two Manual Three Inch Containment Isolation Valves in Bypass Line Were Discovered to Be Locked Open 05000255/LER-2017-0022017-07-17017 July 2017 Reactor Protection System Actuation While the Reactor was Shutdown, LER 17-002-00 for Palisades Regarding Reactor Protection System Actuation While the Reactor was Shutdown 05000255/LER-2017-0012017-05-24024 May 2017 Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions, LER 17-001-00 for Palisades Nuclear Plant Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions PNP 2014-100, Cancellation of Licensee Event Report (LER) 2004-002, Leak Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations2014-11-19019 November 2014 Cancellation of Licensee Event Report (LER) 2004-002, Leak Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations PNP 2011-009, Special Report of Inoperability of Main Steam Line Gross Gamma Activity Monitor2011-02-10010 February 2011 Special Report of Inoperability of Main Steam Line Gross Gamma Activity Monitor ML0726101822007-09-14014 September 2007 Cancellation of Licensee Event Report 07-003, Potential for Reduced Component Cooling Water Cooling Capability ML0609002832006-03-30030 March 2006 Cancellation of Licensee Event Report 05-006, Inoperable Containment Due to Containment Air Cooler Through-Wall Flaws ML18347B2971998-05-19019 May 1998 Submit, NPDES Notification Report, Incident No. Pal-98-05-NC138 for NPDES Permit No MI0001457 Re Difference from Daily Maximum Effluent Limitation for Facility ML18348A9021989-02-0707 February 1989 LER 1988-005-01 for Palisades, Inadequate Procedure Results in Valve Testing During Prohibited Conditions ML18346A2471981-06-19019 June 1981 LER 1981-020-00 for Palisades Nuclear Plant, Pcs Unidentified Leakage Greater than 1.0 Gpm ML18346A2481981-05-13013 May 1981 LER 1981-015-00 for Palisades Nuclear Plant, Safety Injection Tank Boron Concentration ML18346A2491981-02-20020 February 1981 LER 1981-005-00 for Palisades Nuclear Plant, Update - Inoperable Diesel Generator ML18346A2501981-02-19019 February 1981 LER 1981-007-00 for Palisades Nuclear Plant, Inoperable Auxiliary Feedwater Pump ML18346A2511981-01-26026 January 1981 LER 1981-002-00 for Palisades Nuclear Plant, Inadequate Mounting of DC Distribution Panel ML18346A2521981-01-16016 January 1981 LER 1981-001-00 for Palisades Nuclear Plant, During Charging of Station Batteries, Output Breakers of Both Batteries Were Inadvertently Opened for Approximately One Hour ML18346A2531981-01-14014 January 1981 LER 1980-046-00 for Palisades Nuclear Plant, Hydraulic Snubber Failure ML18346A2541981-01-0707 January 1981 LER 1980-045-00 for Palisades Nuclear Plant, Low Condensate Makeup Inventory ML18347A8141980-10-10010 October 1980 LER 1980-037-00 for Palisades Nuclear Plant, Pipe Support Sway Struts Identified to Have the Potential of the Bushing Becoming Loose And/Or Disengaged from the Clamp End of the Sway Strut ML18347A8461980-08-27027 August 1980 License Event Report 1980-027-00 Re Gaseous Release, Extended Due Date of Reporting by Region III on 8/26/1980 ML18347A8471980-08-12012 August 1980 License Event Report 1980-024-00 Re Containment High Radiation Monitor ML18347A8481980-08-0808 August 1980 License Event Report 1980-023-00 Re Containment High Radiation Monitor ML18347A8491980-08-0808 August 1980 License Event Report 1980-022-00 Re Inoperable Nuclear Instrumentation ML18347A8501980-08-0606 August 1980 License Event Report 1980-021-00 Re Misaligned Containment Sump Valve ML18347A8521980-07-29029 July 1980 License Event Report 1980-020-00 Re Misaligned Control Rod ML18347B2071980-06-19019 June 1980 Licensee Event Report 80-018 Regarding Oil Level in Snubber No. 2 Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers ML18347B2081980-06-13013 June 1980 Licensee Event Reports 80-014, 80-015, and 80-016 Regarding Oil Level in Snubbers No. 5, 9, and 7 Were Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers ML18347B2091980-05-15015 May 1980 Licensee Event Report 80-012 Regarding Bottom Half of the Barrier for Fire Penetration HO-12 Was Missing During Inspection of Fire Barriers ML18347B2101980-05-14014 May 1980 License Event Report 1980-011-00 Re Improper Return-to-Service of Porv'S ML18348A9071980-05-12012 May 1980 Submittal of LER 1980-006-00 Purge Valve T-Ring Air Supplies ML18348A9051980-05-12012 May 1980 Submittal of LER 1980-008-00 Update of Valve Leakage ML18347B1411978-09-0606 September 1978 LER 1978-029-00 for Palisades Plant Re Lower Level of Hydrazine in Iodine Removal Tank Due to Approximately 6% of Drainage from the Tank T-102 ML18347B1421978-08-18018 August 1978 LER 1978-028-00 for Palisades Plant Re Containment Building Purge Valve T-Ring in CV-1806 Was Not Pressurized ML18347B1441978-08-11011 August 1978 LER 1978-022-00 for Palisades Plant Re Four Incore Alarms Following Reactor Start-up ML18347B1451978-08-10010 August 1978 LER 1978-021-00 for Palisades Nuclear Plant, Containment Purge Supply Valve CV-1808 Failed to Open During Monthly Test ML18347B1491978-07-20020 July 1978 LER 1978-024-00 & LER 1978-025-00 for Palisades Nuclear Plant, Steam Generator Ph Dropped to 8.02 & One of Two Heaters for T-53B (Concentrated Boric Acid Tank) Failed ML18347B1781978-04-28028 April 1978 License Event Report LER-78-000-00 Re Out-of-Sequence Rod Withdrawal ML18347B1801978-04-19019 April 1978 License Event Report 78-008: Cycle 2 Core Axial Power Distribution Limits of TS 3.10.3 Were Exceeded by Approximately 12% for Steady State Operation During Cycle 2 ML18347B1811978-03-27027 March 1978 License Event Report 1978-007-00 Relates to Electrical Connectors Inside of Containment ML18347B1841978-03-13013 March 1978 Two Updated License Event Reports, LER-78-004 & LER-78-006 ML18348A1951978-03-0202 March 1978 License Event Report 1978-006-00 Re Shipping Cask Movement ML18347B1851978-03-0202 March 1978 License Event Report 1978-005-00 Re Steam Generator Level Instrumentation ML18348A1961978-03-0101 March 1978 License Event Report 1978-004-00 Re Steam Generator Pressure Instrumentation ML18348A1971978-02-0101 February 1978 License Event Report 1977-065-00 Re Operation in a Degraded Mode Permitted by a Limiting Condition for Operation ML18348A1981978-02-0101 February 1978 License Event Report 1978-003-00 Re CV-3025 Failed Closed ML18348A1991978-01-20020 January 1978 LER 1977-063-00 Re Iodine Removal System Hydrazene Tank, LER 1978-001-00 Re Containment Door Interlock Failure & LER 1978-002-00 Re Setpoints of Five Valves Were Outside Band ML18348A2001978-01-0606 January 1978 License Event Report 1977-062-00 Re Iodine Removal System Naoh Tank (T-103) ML18348A2011978-01-0606 January 1978 License Event Report 1977-064-00 Re HPSI Pump P-66B ML18348A2021977-12-21021 December 1977 LER 1977-054-00 Re Four Coincident In-Core Alarms, LER 1977-057-00 Re Pressure Set Point for Channel C, & LER 1977-058-00 Re De-Energized R Bus ML18348A2031977-12-16016 December 1977 License Event Report 1977-055-00 Re Loss of Off-Site Power and Plant Trip 2021-08-13
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- Power company Director of Nuclear Reactor Regulation Att: Mr Robert A. Purple, Chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT, A0-75-25 Attached is Abnormal Occurrence Report A0-75-25 which covers the discovery of an error in a computer program used to set in-core detector alarm limits.
This error could have led to a nonconservative setting of about 2% which is well below the 10% error allowed for in the calculation .
David A. Bixel Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC File
- ABNORMAL OCCURRENCE REPORI' Palisades Plant
- 1. Report Number: A0-75-25, Docket 50-255.
- 2. a. Report Date: November 5, 1975.
- b. Occurrence Date: June 19, 1973 (classified as AO on October 29, 1975).
- 3. Facility: Palisades Plant, Covert, Michigan.
- 4. Identification of Occurrence: Error in computer program used to compute in-core detector alarm limits.
- 5. Conditions Prior to Occurrence: Plant operating at essentially full power.
- 6. Description of Occurrence: Interim Special Technical Specifications, Section 3.c requires that in-core alarms be set to correspond to local power limits used in the ECCS analysis. A ~omputer code is used to com-pute the appropriate in-core alarm limits.
On October 22, 1975 while performing routine checking of data used by the in-core analysis program (INCA), it was noticed that the burnup correction curve for the flux-to-power factors for a particular fuel type had a shape contrary to what might be expected. It was immediately noted that the curve in use would, at this point in time, predict a higher peak power than was actually expected and, hence, was probably conservative. Checking against independent Consumers Power Co diffusion theory calculations confirmed that the curve shape was not as our calculations predicted.
Our fuel supplier, who had generated the flux-to-power factor curves, was then contacted by phone and asked to confirm the shape and range of appli-cability of the curve in burnup. On October 24, 1975 the fuel supplier reported by phone that the burnup correction factor curves for the flux to power factors were accurate. However, the curves for two sets of two fuel types each had been inadvertently interchanged. He suggested changes to be made to the computer program to assign the curves to the correct fuel types. He further stated that, since the correction factors are small and also are similar in shape for all the fuel types, it was his opinion that a maximum nonconservative error of 1 to 2 percent could have occurred over the period that this data had been in use.
The suggested changes were reviewed, implemented in the computer program, and checked by October 28, 1975.
- 7. Designation of Apparent Cause of Occurrence: On May 24, 1973 our fuel supplier sent us a new library of data to be used in the in-core analysis program. The purpose of the revised library was to extend the region of applicability to higher core burnup. This library was reviewed, imple-mented and tested. It was put into production use on June 19, 1973.
- The burnup correction curves for the flux-to-power factors which were in-cluded in this library had been, in some cases, inadvertently assigned to the wrong fuel types. At the time of implementation, the error was about 2 percent. Since this is the same magnitude as the difference ex-pected due to the intended library revision, it was not detected in cross-checking. Later, when the error became more significant (6.5 percent in the conservative direction), it was caught by normal Consumers Power Co core follow checking.
- 8. Analysis of Occurrence: The error was corrected as explained in Item 6 above.
The most current in-core data was immediately rerun. The peak kW/ft in the core as predicted by the code dropped 6.5 percent. The correction factor curves were then plotted and ratioed. From inspection of the curves, when appropriate fuel exposures were taken into account, it appears that the maximum nonconservative error occurred immediately at the time of first implementation of the new library. This was June 19, 1973. In-core data from this case was rerun with the corrected code and the error determined to be 2 percent nonconservative. It appears that from this point on the error moved steadily toward the conservative direction ending at approxi-mately 6.5 percent conservative on October 24, 1975.
We conclude that there were no significant potential consequences to the health and safety of the public for the following reasons. First, the core
- has rarely been operated within 2 percent of the limits stated in Interim Special Technical Specifications, Section 3.a. For instance, on June 19, 1973 when the maximum nonconserviative error occurred, we were actually operating 12 percent under the limits of Section 3.a. Second, Section 3.a carries a factor of 10 percent to account for measurement-calculational uncertainty. At no time was the error as large as 10 percent nonconservative.
Corrective Action: The code was immediately corrected as described in Items 6 and 7 above. Since the error, at the time of discovery, was in the conservative direction, no immediate corrective action in the area of core operation was required.
Our fuel manufacturer states that since May 24, 1973 they have implemented a Quality Assurance program that should catch this type of error. If the error in the conversion .constants exceeds a detectable level (ie, 5 to 7 percent), Consumers Power Company core follow activities, as demonstrated, will detect the error. This occurrence demonstrates the purpose of core follow activities as conducted by Consumers Power Company in assuring that such errors do not exceed the 10 percent uncertainty which is factored into the in-core limits.
- 10. Failure Data: Not applicable .
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