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Category:Letter
MONTHYEARML24320A1232024-11-18018 November 2024 Confirmation of Initial License Examination IR 05000255/20240122024-11-12012 November 2024 Restart Inspection Report 05000255/2024012 ML24312A2262024-11-0606 November 2024 Letter from C. Nelson, Michigan SHPO Regarding Palisades Nuclear Plant Architectural Survey ML24310A0142024-11-0505 November 2024 Ape Notification to Mackinac Bands of Chippewa Palisades ML24310A0132024-11-0505 November 2024 Ape Notification to Grand River Bands of Ottawa Indians Palisades ML24292A1572024-11-0505 November 2024 Ape Notification to Burt Lake Band Palisades ML24309A1872024-11-0404 November 2024 Ape Notification to Grand Portage Band of Lake Superior Chippewa Palisades ML24309A2102024-11-0404 November 2024 Ape Notification to Saginaw Chippewa Indian Tribe of Michigan Palisades ML24309A2122024-11-0404 November 2024 Ape Notification to Sault Ste. Marie Tribe of Chippewa Indians Palisades ML24309A1912024-11-0404 November 2024 Ape Notification to Lac Du Flambeau Band of Lake Superior Chippewa Indians Palisades ML24309A1832024-11-0404 November 2024 Ape Notification to Bois Forte Band of the Minnesota Chippewa Tribe Palisades ML24309A2112024-11-0404 November 2024 Ape Notification to Saint Croix Chippewa Indians of Wisconsin Palisades ML24309A2132024-11-0404 November 2024 Ape Notification to Turtle Mountain Band of Chippewa Indians Palisades ML24309A2082024-11-0404 November 2024 Ape Notification to Red Cliff Band of Lake Superior Chippewa Indians Palisades ML24292A0492024-11-0404 November 2024 Ape Notification to Bad River Band of the Lake Superior Tribe of Chippewa Indians Palisades ML24309A2092024-11-0404 November 2024 Ape Notification to Red Lake Band of Chippewa Indians Palisades ML24309A2032024-11-0404 November 2024 Ape Notification to Ottawa Tribe of Oklahoma Palisades ML24309A1862024-11-0404 November 2024 Ape Notification to Forest County Potawatomi Community Palisades ML24309A1842024-11-0404 November 2024 Ape Notification to Chippewa Cree Indians of the Rocky Boys Reservation of Montana Palisades ML24309A1952024-11-0404 November 2024 Ape Notification to Little River Band of Ottawa Indians Palisades ML24309A1902024-11-0404 November 2024 Ape Notification to Lac Courte Oreilles Band of Lake Superior Chippewa Palisades ML24309A2022024-11-0404 November 2024 Ape Notification to Nottawaseppi Huron Band of the Potawatomi Palisades ML24309A2052024-11-0404 November 2024 Ape Notification to Prairie Band Potawatomi Nation Palisades ML24309A1972024-11-0404 November 2024 Ape Notification to Little Traverse Bay Bands of Odawa Indians Palisades ML24309A2002024-11-0404 November 2024 Ape Notification to Miami Tribe of Oklahoma Palisades ML24309A1982024-11-0404 November 2024 Ape Notification to Match E Be Nash She Wish Band of Pottawatomi Indians Palisades ML24309A1922024-11-0404 November 2024 Ape Notification to Lac Vieux Desert Band of Lk Superior Chippewa Indians Palisades ML24309A2072024-11-0404 November 2024 Ape Notification to Quechan Tribe of the Fort Yuma Indian Reservation Palisades ML24309A1992024-11-0404 November 2024 Ape Notification to Menominee Indian Tribe of Wisconsin Palisades ML24309A1882024-11-0404 November 2024 Ape Notification to Grand Traverse Band of Ottawa and Chippewa Indians Palisades ML24309A2012024-11-0404 November 2024 Ape Notification to Mille Lacs Band of Ojibwe Palisades ML24309A1822024-11-0404 November 2024 Ape Notification to Bay Mills Indian Community Palisades ML24309A2042024-11-0404 November 2024 Ape Notification to Pokagon Band of Potawatomi Indians Palisades ML24309A1892024-11-0404 November 2024 Ape Notification to Hannahville Indian Community Palisades ML24309A1852024-11-0404 November 2024 Ape Notification to Citizen Potawatomi Nation Palisades ML24292A0072024-11-0404 November 2024 Ape Notification to Achp Palisades ML24309A1932024-11-0404 November 2024 Ape Notification to Leech Lake Band of Ojibwe Palisades ML24309A2142024-11-0404 November 2024 Ape Notification to White Earth Band of Minnesota Chippewa Tribe Palisades ML24309A2062024-11-0404 November 2024 Ape Notification to Prairie Island Indian Community Palisades PNP 2024-014, Request for USNRC to Rescind Approved Exemption Requests for 140.11(a)(4) and 50.54(w)(1), Reduction of Insurances2024-10-0909 October 2024 Request for USNRC to Rescind Approved Exemption Requests for 140.11(a)(4) and 50.54(w)(1), Reduction of Insurances PNP 2024-037, Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-0202024-10-0404 October 2024 Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-020 ML24267A2962024-10-0101 October 2024 Summary of Conference Call Regarding Steam Generator Tube Inspections ML24263A1712024-09-20020 September 2024 Environmental Request for Additional Information ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24219A4202024-09-12012 September 2024 Change in Estimated Hours and Review Schedule for Licensing Actions Submitted to Support Resumption of Power Operations (Epids L-2023-LLE-0025, L-2023-LLM-0005, L-2023-LLA-0174, L-2024-LLA-0013, L-2024-LLA-0060, L-2024-LLA-0071) IR 05000255/20244022024-09-0606 September 2024 Public: Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2024402 PNP 2024-029, Notice of Payroll Transition at Palisades Nuclear Plant2024-08-15015 August 2024 Notice of Payroll Transition at Palisades Nuclear Plant IR 05000255/20240022024-08-0909 August 2024 NRC Inspection Report No. 05000255/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 PNP 2024-032, Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations2024-07-31031 July 2024 Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations 2024-09-06
[Table view] 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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Text
consumers
~\egu\atory Docket f\\e.
General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201
...~----"'---.. ---
D~cember 21, 1976 ,, .
I;*\' *
. :;*. /
Mr James G Keppler . .
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Office of Inspection & Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE *DPR
- PALISADES PLANT, ER-76~45 -
DBA SEQUENCER Attached is a Licensee Event Report relating to the Palisades Plant. This report concerns failure of part of the automatic sequencer designed to place safety system loads on the emergency diesel generator *. These safety systems could have been manually started should that have been required.
David A Bixel Assistant Nuclear Licensing Administrator DEC 2 3 1976
e LICENSEE EVENT REPORT- Palisades Plant
. 'CONTROL BLOCK: I I I I I I I [PLEASE PRINT ALL REQUIRED INFORMATION]
1 6 LICENSE EVENT LICENSE NUMBER TYPE TYPE I ol ol-1 ol ol ol ol ol-1 ol ol 14111111111. lol1I 15 25 26 30 31 32 REPORT REPORT TYPE. SOURCE OOCKF;T NUMBER EVENT DATE REPORT DATE *
@IT]coN'T I *I *I l1.J L1J I ol sl ol-1ol21 sl sl I ii 2 I o I 2 I 1 I 6 I l1l2l2l1l 1l 6I 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION
~!During a rerun of a test (to check other equipment) which was successfully conducted I 7 8 9 80 lol31 Iabout one day earlier; DBA seguencer 34-1 failed to operate. In accordance with the I 7 8 9 80 lol41 I Technical Specifications the redundant channel was then tested and similarly DBA se~ I 7 8 9 80 10151 7 8 I guencer 9 . .
34-2 failed to operate. With this second failure a standard (normal) plant I 80 lol61 I shutdown was commenced. See attached Event Description for more details. (ER-76-45) I 7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION 7
@0 IE! El 8 9 10 l!....J 11 I I I N I s I T I R j .u I 12 17 w 43 IE I 0 I 2 I 0 I 44 47 L.!.J 48 CAUSE DESCRIPTION lol0I I The sequencer clutch failed to reset due to insufficient clutch disk gap. The most *I 7 8 9 80 lolsl I probable cause of the disk gap problem was set screw slippage. See Event Description I 7 8 9 80
~ITIQI I for additional details. I
~9 . FACILITY METHOD OF 80 STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION
[ill] L!J 9
l1lolol 10 . . 12 NA I L£.I NA I 7 8 13 44 45 46 .80 FORM OF rn w ACTIVITY CONTENT RELEASED UJ _,________
OF RELEASE AMOUNT OF ACTIVITY
_I LOCATION OF RELEASE 7 8 9 PERSONNEL EXPOSURES 10 11 NA 44 ~-----------------------------------------*
45 NA 80 NUMBER TYPE DESCRIPTION DE] Lo I oIo I ~ NA 7 8 9 11 12 13 80 PERSDNNEL INJURIES NUMBER DESCRIPTION EE!lololol NA 7 8 9 11 12 80
. --Probable Consequences ~
IIIfil I If an SIS would have occurred and standby power were not available (Contd on Line 18) 7 8 9 80 LOSS OR DAMAGE TO FACILITY fifil w TYPE DESCRIPTION NA
'7 8 9 10 PUBLICITY EJZl None 7 8 9
~ I( Contd From Line l5) some safety-related equipment would have had to be manually started.j 7 8 9 80.
7illfil89~*--------------------------------------------------------------------------------------------------~ 00
- LICENSEE EVENT REPORT ER-76-45 Docket 50-255 Continuation of Event Description
Background
On December 8, 1976, the quarterly safeguards test (Q0-1) was conducted success-fully except for one discrepancy (charging pump P55C should not have started).
Part of the evaluation of this deviation required a rerun of a portion of the test to verify the cause of the pump start. At 1118 hours0.0129 days <br />0.311 hours <br />0.00185 weeks <br />4.25399e-4 months <br /> on December 9, the test was run and it was found that one of the two left .channel DBA sequencers (34-1) failed to operate. Repair personnel were promptly notified of the problem and cor-rective action was initiated.
Initial Action In accordance with Technical Specifications, the operability of the right channel SIS/DBA sequencer was determined prior to commencing the repair of the left chan-nel. At 1222 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.64971e-4 months <br />, the right channel portion of Q0-1 was run and it was found that one of the two right channel sequencers (34-2) also failed to operate. Based on this additional failure, reactor shutdown was commenced and the normal shutdown rate was established by 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br />. Concurrent with the shutdown, repair of the right channel sequencer was begun.
Findings Upon inspection of the sequencer, it was determined that the clutch was still engaged and that the unit had failed to reset. The unit was reset and the clutch gap adjusted. At approximately. 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br /> the right channel portion of Q0-1 was run to verify proper operation of 34-2. The test was successful and proper reset of the unit was observed. The test was rerun a second time and again successful operation of the unit was observed.
Upon completion of repair and testing of the right channel, the failed left chan-nel sequencer (34-1) was investigated. The unit was found to have the same prob-lems as 34-2 and it was repaired and tested. By approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, both channels had been repaired, tested, and returned to service.
Evaluation and Follow-Up The clutch disk assemblies for sequencers 34-2 and 34-1 had been previously re-placed and adjusted on October 5, 1976 and October 14, 1976, respectively. At this time, the clutch disk clearance was set at approximately 0.020". The unit was tested several times and Q0-1 was used for the operational check of the com-pleted work. Satisfactory operation was obtained in each case. (It should be noted that the clutch disk gap setting is the result of a trade off between (1) a large gap which insures easy resetting of the unit and (2) a small gap which results in greater spring tension producing a minimum of clutch slippage.)
- Since the operability of the unit was demonstrated several times after the clutch replacement, it is concluded that the clearances set during the clutch replacement were adequate. The clutch gap apparently changed during the two months following the repair preventing clutch disengagement.
Subsequent to resetting the clutch disk gap after this event, the set screws for the clutch collars were further tightened to minimize the possibility of recurrence.
In addition to the mechanical adjustment discussed above, temporary procedural controls will be instituted. For test situations requiring operation of the sequences, the sequencers will be visually inspected after sequencer operation to insure that the reset function of each unit performs satisfactorily .