ML052030135
| ML052030135 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/26/2004 |
| From: | Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2004-0282 | |
| Download: ML052030135 (2) | |
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, . DAY Point Beach Refueling D53 Outage Edition May 26, 2004 CONTACT INFORMATION Control Room Emergency - x2911 EMT Pager 6442 Work Control Center - x6703 OCC - x 7190 - Option I Lessons Learned - x7190 - Option 2 Plant Status - x7190 - Option 3 Accomplishments
- SIG Primary Manway Installation
. Cavity Seal Ring Removal
- Exit Reduced Inventory
. Installed Thimbles
- Removed Reactor Head Stud Hole Covers
- Installed Reactor Head Bolts I---
1
- Aligned 1PI B Reactor Coolant Pump Personnel Last 24 Hours Outage to Safety Last_24_Hour Date Schedule Focus Areas/Priorities zc Recordable - 0 Recordable - I1 Disabling -0 Disabling - 0 . Reactor Head Penetration #26 Relief Request Issues
. Seal Table Restoration
- OSHA Recordable - Back strain.
- Tension Reactor Head Studs
. Enter Mode 5
- Install Pressurizer Manway Lst 24 Hours Outage to Date . Couple 1P1 B Reactor Coolant Pump
- Install Conoseals ALARA 'w ' 1.987 79.189 R Dose as of the end of Day 51
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May 26, 2004 OUTAGE GOALS NUCLEAR SAFETY GOAL ACTUAL HUMAN PERFORMANCE GOAL ACTUAL PERFORMANCE____
Unplanned orangelred paths None None Security Violations s12 loggable events 3 Reactor trips (either unit) None I Station hurnan performance clod( None 4 resets _ _ _ _ _ _
Safeguards actuation (either unit) None None Rework 1% On Goal Loss of shutdown cooling None None SCHEDULE PERFORMANCE Outage Duration Loss of Rx vessel level control None None (excludes extensions due to s 30 days Off Goal extended head or BMI Inspections)_
INDUSTRIAL SAFETY Mod Implementation 100% of Rev 0 On Goal PERFORMANCE
>85% schedule Lost time accidents None None Schedule Compliance compliance with Off Goal outage milestone Personnel Injuries (OSHA recordable) None I Emergent work (during s 2%Wte additions On Goal Implementation) s 5%Emergent RADIOLOGICAL PERFORMANCE ScpeComplete Z95% of On Goal Rev 0 scope Radiation exposure (Excludes additional 100% of Scheduled dose from any head or BMI repair s 92 R 79.189 R Operator Burdens Operator Burdens On Goal contingencies) cornmpte Personnel contaminations 5 18 WI 10 Post Outage availability 2150 days continuous of operation Available at a later date Radiological events (defined as unplanned uptake w/assigned dose >10 mrem or s1 event 1 BUDGET PERFORMANCE Within -2%budget to Oh of Seriously dose event based on ED alarms I outage Challenged Radmaterlal event (defined as any rad 1 event 0 material outside RCAk 100 CPM) ___vet_
Human Performance Operating Experience Job observations are the trendy' thing to do. So what OE12440 - Reactor Vessel Conoseal Leakage And happens to all of the information collected in Assembly Issues observations? We are able to collect the data and trend it On March 15, 2001, in response to indications of elevated to see where areas for improvement may lie. This done RCS leak rate, technicians entered the Containment using the PACE program. The PACE database provides Building and noted crystallized boric acid accumulation us with focus areas for improvement that may allow us to prevent a more serious problem in the future. These around the perimeter of the lower Conoseal clamp of trends also show us what we are doing well. Conoseal Assembly Number 4 on the Reactor Vessel head. Engineering evaluated the leakage in accordance with guidance provided by EPRI and determined that the leak rate was minor, established monitoring and acceptance criteria, and judged continued operation until an impending refueling outage scheduled to start on April 27. Upon disassembly of the mating surfaces and Safety Snippet gasket during the outage it was noted that the gasket had a dent mark and an apparent crushed burr on the outer Just a reminder to be told, balance that loadl edge. There were no apparent deformations on either the male or female flange surfaces of the assembly, and it was OE1 0902 March 2000, Seabrook - Electricians were determined the leakage was likely due to the introduction offloading battery cells from a metal pallet on a forklift of metal particulate/grit between the mating surfaces The offload sequence went from inside, closest to the during reassemble the previous refueling outage.
forklift, to the outside, furthest from it. The result -
instability in the load and the pallet tipped under the Lessons Learned: The root cause was determined to weight of the batteries. The cells fractured spilling 19 be Inadequate procedural guidance In both oversight gallons of sulfuric acid/water electrolyte in the switchgear and verification of the assembly process. Also, the room. ThisOEisnotjustforbafferyremoval. Balanceall procedure did not contain adequate guidance for the yourloads. torque sequence for the final assembly.