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| {{#Wiki_filter:_ ..... * * | | {{#Wiki_filter:.'~- ~,.. _ ..... |
| * consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 | | consumers |
| * Area Code 517 788-0550 January 4, 1977 Mr James G Keppler Office of Inspection | | * Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 |
| & Enforcement Region III US Nuclear Regulatory Commission 799 Roo*sevelt Road Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR-20 -PALISADES PLANT, ER-76-44 -SG TRIP SET POINT DRIFT Attached is a Reportable Event which relates to the Palisades Plant Reactor Protection System (RPS) Steam Generator (SG) low level trip set point. The set point on one channel was found to have drifted 0.135 inch.below the ceptable value. David A Bixel Assistant Nuclear Licensing Administrator JAN 6 1977 9LJCENSEE EVENT REPORT e Palisades CONTROL BLOCK: I 1 I I I I I I . [PLEASE PAINT ALL REQUIRED INFORMATION] | | * Area Code 517 788-0550 January 4, 1977 Mr James G Keppler Office of Inspection & Enforcement Region III US Nuclear Regulatory Commission 799 Roo*sevelt Road Glen Ellyn, IL 60137 |
| 6 LICENSEE | | * DOCKET 50-255, LICENSE DPR PALISADES PLANT, ER-76 SG TRIP SET POINT DRIFT Attached is a Reportable Event which relates to the Palisades Plant Reactor Protection System (RPS) Steam Generator (SG) low level trip set point. The set point on one channel was found to have drifted 0.135 inch.below the ac-ceptable value. |
| * NAME IMIIIPIAILl1I LICENSE NUMBER Iola I-lo-I ol ol ol ol-lo lo I . 7 8 9 14 15 25 REPORT 'REPORT LICENSE TYPE I 4 I 1 11 I 1 I 1 I 26 30 TYPE. SOURCE . OOCKET NUMBER EVENT DATE EVENT TYPE Io I 3 I 31 32 REPORT DATE @E]coN'T l* .. 7 8 57 59* L1J l1.J lo,15 lo I-lo 1215151 L1l 2I ol 617 16 I 1011101417171 59 60 N 75 80 EVENT DESCRIPTION lof2I I During monthly testing of the RPS, the SG low level trip set point (Channel D) was | | David A Bixel Assistant Nuclear Licensing Administrator |
| * I 7. a*s | | * JAN 6 1977 |
| * 80 lol3l I found to be below the' Tech Spec limit by 0.135 inch. The other three channels were I 7 8 9 . . . BO lol41. I normal. In *addition, a review of this event disclosed that a similar set point 7 8 9 drift .I 80 lol51 l had occurred on 9-2-76 but was not reported due to an error in the calculation. | | |
| In I 7 8 9 . . lolsl I both instances the set 7 B s point was. returned to the* proper ( ER-76-044) (Contd on Line 1.8) | | 9LJCENSEE EVENT REPORT e Palisades CONTROL BLOCK: I I I I I I I . [PLEASE PAINT ALL REQUIRED INFORMATION] |
| * t, SYSTEM CODE CAUSE CODE COMPONENT CODE PRIME. COMPONENT SUPPLIER COMPONENT MANUFACTURER VIOLATION 80 rl Al w I I I N I 8 I Tl R I u I .w I z I 2 I 2 I 2 I w 1 a s 10 11 12 17 43 44 47 48 CAUSE . DESCRIPTION | | 1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE |
| *' Iola! I The cause: of this event was both set point drift and an administrative limit that was I . lolsj | | * IMIIIPIAILl1I Iola I-lo-I ol ol ol ol-lo lo I I 4 I 1 11 I1 I1 I Io I 3 I |
| * 0 j : filll 7 a rn FACIUTY* STATUS LU 9 FORM OF %. POWER OTHER STATus* 1. i I 0 I 0 I .,,_I_* -"""NA""-- | | . 7 8 9 14 15 25 26 30 31 32 REPORT 'REPORT TYPE. SOURCE . OOCKET NUMBER EVENT DATE REPORT DATE |
| _ _..,,.I 10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE I AMOUNT OF ACTIVITY METHOD OF OISCOVERY w 45 7 8 . .* ___ N_A ____ _.,. s* 10 11 | | @E]coN'T l*.. ]-*~I L1J l1.J lo,15 lo I-lo 1215151 L1l 2I ol 617 16 I 1011101417171 7 8 57 59* 59 60 ~- *~-~ N 75 80 EVENT DESCRIPTION lof2I I During monthly testing of the RPS, the SG low level trip set point (Channel D) was |
| * 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ol olol NA 7 as 11 12 | | * I |
| * 13 . PERS.ONNEL INJURIES NUMBER DESCRIPTION | | : 7. a*s |
| *[EI I 0 I 0 I 0 I NA 7 8 9 . 11 12 . --*---. ----.. . -... PROBABLE CONSEQUENCES I None; the other cha.Iu:iels were found acceptable. | | * 80 lol3l I found to be below the' Tech Spec limit by 0.135 inch. The other three channels were I 7 8 9 . . . BO lol41. I normal. In *addition, a review of this event disclosed that a similar set point drift .I 7 8 9 80 lol51 l had occurred on 9-2-76 but was not reported due to an error in the calculation. In I 7 8 9 . . ~ |
| 1 as | | lolsl I both instances the set point was. returned to the* proper ( ER-76-044) (Contd on Line 1.8) |
| * LOSS . OR* DAMAGE TO FACILITY . TYPE DESCRIPTION | | * t, 7 B s PRIME. 80 SYSTEM CAUSE COMPONENT COMPONENT w |
| [Ifil NA 7 as 10 PUBLICITY I Norie :DDITIONAL FACTORS DISCOVERY DESCRIPTION | | CODE SUPPLIER MANUFACTURER VIOLATION |
| *.NA I 46 80 LOCATION OF RELEASE NA 80 80 80 I 80 80 80 E1fil I ( Contd From Line 6) value . 7 8 9 A review of the administrative set point limit indicated I 80 G]] I that it was too close to the Tech Spec limit. The administrative limit is being I 7 8 9 80 appropriately revised.}}
| | .w CODE COMPONENT CODE 1 |
| | ~I a s 10 rl Al 11 I I I NI 8 I 12 Tl R I u I 17 43 Iz I2 I2 I2 I 44 47 w48 CAUSE . DESCRIPTION |
| | *' |
| | Iola! I The cause: of this event was both set point drift and an administrative limit that was I. |
| | lolsj j.~cl~~~ -t~- th~--T~-c*li-8J,e'c*-1imit-.~----------------~----*-~------- |
| | * 0 j |
| | ~: FACIUTY* |
| | %. POWER OTHER STATus* |
| | METHOD OF OISCOVERY DISCOVERY DESCRIPTION |
| | : |
| | w STATUS fillla LU 1. i I 0 I 0 I .,,_I_*-"""NA""--_ _..,,.I *.NA |
| | ...__~~~=-=-~~~~~~~~___,* |
| | I 7 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT I |
| | rn RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE |
| | ~ . -~ .* ~-*_ _ _N_A_ _ _ __.,. NA 7 8 s* 10 11 |
| | * 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION |
| | ~I ol olol ~ NA 7 as 11 12 |
| | * 13 80 |
| | . PERS.ONNEL INJURIES NUMBER DESCRIPTION |
| | *[EI I 0 I 0 I 0 I NA 7 8 9 . 11 12 80 |
| | . - -*- - - . -- - - .. . - ... |
| | PROBABLE CONSEQUENCES |
| | ~ I None; the other cha.Iu:iels were found acceptable. I 1 as |
| | * 80 LOSS . OR* DAMAGE TO FACILITY |
| | . TYPE DESCRIPTION |
| | [Ifil ~ NA I |
| | 7 as 10 80 PUBLICITY Norie 80 |
| | :DDITIONAL FACTORS E1fil I ( Contd From Line 6) value . A review of the administrative set point limit indicated I 7 8 9 80 G]] I that it was too close to the Tech Spec limit. The administrative limit is being I 7 8 9 80 appropriately revised.}} |
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Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML18344A4142018-12-10010 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 ML18348A1981978-02-0101 February 1978 License Event Report 1978-003-00 Re CV-3025 Failed Closed ML18348A1971978-02-0101 February 1978 License Event Report 1977-065-00 Re Operation in a Degraded Mode Permitted by a Limiting Condition for Operation 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 ML18348A2041977-12-12012 December 1977 License Event Report 1977-056-00 Re Gaseous Waste Discharge 2018-12-10
[Table view] |
Text
.'~- ~,.. _ .....
consumers
- Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 January 4, 1977 Mr James G Keppler Office of Inspection & Enforcement Region III US Nuclear Regulatory Commission 799 Roo*sevelt Road Glen Ellyn, IL 60137
- DOCKET 50-255, LICENSE DPR PALISADES PLANT, ER-76 SG TRIP SET POINT DRIFT Attached is a Reportable Event which relates to the Palisades Plant Reactor Protection System (RPS) Steam Generator (SG) low level trip set point. The set point on one channel was found to have drifted 0.135 inch.below the ac-ceptable value.
David A Bixel Assistant Nuclear Licensing Administrator
9LJCENSEE EVENT REPORT e Palisades CONTROL BLOCK: I I I I I I I . [PLEASE PAINT ALL REQUIRED INFORMATION]
1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE
- IMIIIPIAILl1I Iola I-lo-I ol ol ol ol-lo lo I I 4 I 1 11 I1 I1 I Io I 3 I
. 7 8 9 14 15 25 26 30 31 32 REPORT 'REPORT TYPE. SOURCE . OOCKET NUMBER EVENT DATE REPORT DATE
@E]coN'T l*.. ]-*~I L1J l1.J lo,15 lo I-lo 1215151 L1l 2I ol 617 16 I 1011101417171 7 8 57 59* 59 60 ~- *~-~ N 75 80 EVENT DESCRIPTION lof2I I During monthly testing of the RPS, the SG low level trip set point (Channel D) was
- 7. a*s
- 80 lol3l I found to be below the' Tech Spec limit by 0.135 inch. The other three channels were I 7 8 9 . . . BO lol41. I normal. In *addition, a review of this event disclosed that a similar set point drift .I 7 8 9 80 lol51 l had occurred on 9-2-76 but was not reported due to an error in the calculation. In I 7 8 9 . . ~
lolsl I both instances the set point was. returned to the* proper ( ER-76-044) (Contd on Line 1.8)
- t, 7 B s PRIME. 80 SYSTEM CAUSE COMPONENT COMPONENT w
CODE SUPPLIER MANUFACTURER VIOLATION
.w CODE COMPONENT CODE 1
~I a s 10 rl Al 11 I I I NI 8 I 12 Tl R I u I 17 43 Iz I2 I2 I2 I 44 47 w48 CAUSE . DESCRIPTION
Iola! I The cause: of this event was both set point drift and an administrative limit that was I.
lolsj j.~cl~~~ -t~- th~--T~-c*li-8J,e'c*-1imit-.~----------------~----*-~-------
~: FACIUTY*
%. POWER OTHER STATus*
METHOD OF OISCOVERY DISCOVERY DESCRIPTION
w STATUS fillla LU 1. i I 0 I 0 I .,,_I_*-"""NA""--_ _..,,.I *.NA
...__~~~=-=-~~~~~~~~___,*
I 7 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT I
rn RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE
~ . -~ .* ~-*_ _ _N_A_ _ _ __.,. NA 7 8 s* 10 11
- 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~I ol olol ~ NA 7 as 11 12
. PERS.ONNEL INJURIES NUMBER DESCRIPTION
- [EI I 0 I 0 I 0 I NA 7 8 9 . 11 12 80
. - -*- - - . -- - - .. . - ...
PROBABLE CONSEQUENCES
~ I None; the other cha.Iu:iels were found acceptable. I 1 as
- 80 LOSS . OR* DAMAGE TO FACILITY
. TYPE DESCRIPTION
[Ifil ~ NA I
7 as 10 80 PUBLICITY Norie 80
- DDITIONAL FACTORS E1fil I ( Contd From Line 6) value . A review of the administrative set point limit indicated I 7 8 9 80 G]] I that it was too close to the Tech Spec limit. The administrative limit is being I 7 8 9 80 appropriately revised.