RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .
RS-24-102, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591
RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
IR 05000237/2024003
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RS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)
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RS-24-104, Nuclear Radiological Emergency Plan Document Revision
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RS-24-135, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
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05000249/LER-2024-002, Low Pressure Coolant Injection Pump Suction Relief Valve Inoperable as a Primary Containment Isolated Valve Resulted in a Condition Prohibited by Technical Specifications
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05000237/LER-2024-001, Containment Cooling Service Water Valve Failure Resulted in a Condition Prohibited by Technical Specifications and Loss of Safety Function
05000249/LER-2024-002, Low Pressure Coolant Injection Pump Suction Relief Valve Inoperable as a Primary Containment Isolated Valve Resulted in a Condition Prohibited by Technical Specifications
05000237/LER-2024-001, Containment Cooling Service Water Valve Failure Resulted in a Condition Prohibited by Technical Specifications and Loss of Safety Function
'Chicago, Illinois 60690 BBS Ltr. #32-75 Dresden Nuclear R. R. #1 Morris, Illinois January 16, 19
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Mr. James G. Keppler, Regional Director Directorate of Regulatory Operations-Region III U. s. Atomic Energy Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 S~T: REPORT OF ABNORMAL OCCURRENCE PER SECTION 6.6.A OF THE TECHNICAL SPECIFICATIONS HYDRAULIC PIPING RESTRAINT FAILURE
2) Notification of Region III of AEC Regulatory Operations Telephone: Mr. P. Johnson, 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br /> on January 6, 1975 Telegram:
f'1r. James G. Keppler, 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />.on January 6, 1975
3) Report 50-237/1974-53, Inspection of Bergen~Paterson Shock Suppressors Report Number:
50-249/1975-1 Report Date:
January 16, 1975 Occurrence Date:
January 4, 1975 Facility: Dresden Nuclear Power Station, Morris, Illinois IDENTIFICATION OF OCCURRENCE When Unit 3 was shutdown on January 3, 1975, an inspection was made of all thirty-five snubbers in the drywell.
The inspection of the Bergen Paterson shock suppressors on January 4, 1975, revealed that eight snubbers were low on oil with two of them considered inoperable. This condition could have prevented.the performance of the intended safety function of an engineered safety feature system.
CONDITIONS PRIOR TO OCCURRENCE Unit 3 was in the shutdown mode at the time of the inspection.
The last inspection of the drywell snubbers was made about 105 days prior to this inspection.
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Mr. James G. Keppler
,r*' ruary 16,
1975 The inoperablesnubbers were found duriilg a routine inspection during unit shutdown.
The results of the inspections on the eight low snubbers are given in the following table.
Feedwater Line Line 34 2.511 3.511 (iow) 3A Target Rock Safety Valve 35 2.7511 4.2511 (low) 3A Target Rock Safety Valve Note:
The seal material for the above eight snubbers is ethylene propylene.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE (Equipment Failure)
The two inoperablesnubbers were removed from the drywell and disassembled for a more thorough examination. This inspection revealed that the 0-ring's were pinched, the seals showed slight deterioration and the cylinder was scratched.
No singular cause can be assigned as mode of failure, rather all of the aforementioned problems contributed to the loss of oil from the snubbe~~
ANALYSIS OF OCCURRENCE The two inoperablesnubbers did not threaten the health and safety of the public.
The two inoperablesnubbers were replaced with rebuilt snubbers containing ethylene propylene seal material and oil was added to the other six snubbers
Mr. James.*:ith~nerl. da;.
An inspection was made of the eight snubbers to verify proper operation prior to start up.
FAILURE DATA Most of snubber failures in the past were related.to the usage of polyurethane seal material. This occurrence has no singular cause, but is attributable to the several minor problems which allowed an excessive oil leak.age condition to exist during the 105 day operating period between inspections.
On January 16, 1975, Mr. R. Knop of.AF.c Region III was notified that this Abnormal Occurrence report would be submitted 12 days after the date of occurrence due to extended review of the problem.
Letter Enclosing LER 75-048-01 Regarding Current Status of a Long-Term Corrective Action to Prevent Reoccurrence of a Through-Wall Crack in the Drywell-Torus Nitrogen Purge Line 1604-18