ML051890459
| ML051890459 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/06/2004 |
| From: | Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2004-0282 | |
| Download: ML051890459 (6) | |
Text
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NMC Committed to Nucdear Eircli ence Point Beah Nuclear -P Point Beach Nuclear Plant
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V U1R28 OCC Interactive Turnover Meeting Agenda Tuesday, Apt-l 06, 2004 Start Time:
Attendees:
/ 1800, Shift Outage Directors (SOD)
Shift Outage Managers (SOM)
Operations Coordinators (SOC)
Maintenance Coordinators (MOC)
Engineer Coordinators (EOM)
Major Project Coordinators (MPC)
NSB 217 Rad Protection Manager (RPM)
- Chemistry Manager IC General Supervisor Electrical General Supervisor Mechanical General Supervisor Supply Chain Manager Installation Services General
- a. 9 CZ-I 1 Expected Duration: 30 Minutes Agenda:
- 1. Safety Issue Discussion (SOD)
- 2.
- 3. Plant Status / Operations Coordinator Turnover (SOC)
- 4. Shutdown Safety Assessment (SOC)
S.
Maintenance Coordinator Turnover (MOC)
- 6. Engineering Coordinator Turnover (EOC)
- 7.
Major Projects Coordinator Turnover (MPC)
- 8. Rapid Trending Assessment (NOS)
- 9. Action Item Review (SOM)
LO.
Critical Path (SOM)
- 11. Shift Goals (SOM)
L2.
ACEMAN Assessment (SOM)
L3.
Final Comments (SOD) ided In Dally Package:
Safety Snippet Outage Alara Report Daily Outage Status Report Shutdown Safety Assessment Medium/High Risk Activities Defined Critical Path Review Daily Outage OE A4*A1W
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- hI1ltM Point Beach Nuclear Plant U1R28 Refueling Outage This week's theme Is Close Calls or more specifically, what we call near misses. Learning from close calls should be looked on as golden opportunities to prevent actual accidents. Let's not miss out on this opportunity.
"Fix the danwer-save a stranger-OE from U1 R27 -A compressed gas cylinder In containment stored In a walkway, was not secured. The cylinder was bumped by a worker and fell over. Fortunately a co-worker noticed the sItuatIon and caught the cylinder before any damage could be done. Are all of our compressed gas cylinders secured?
'When you foil to report a hazardous condition, you may contribute to employee attrition" Near-miss failure story:
A co-worker Is using a ladder. It seems fine, but as he comes down, one of the rungs sags as he steps on It. He notices a crack. He puts the ladder back without tagging It as needing repairs. The next day you grab the same ladder. As you start to climb you put your foot through the rung, lose your balance and fall, spraining your ankle.
Do you check your ladder before you climb?
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"Report and repair or someone mray despair' OE17263 Comanche Peak-Aworkerleaned back in his chairwhenthe screws holdingthe back ofthe chairto the body separated and he fell back to the floor. Examination of the chair found that only a single screw was holding It together. By someone not reporting this situation, a lost time accident occurred.
WSidestepping a hazardous condition leaves others at risk of hospital admfissaon A worker was attempting to remove a water tank from a piece of heavy equipment. He was removing some bolts not realizing that they were the only support for the heavy tank itself. When the last bolt came out, the 1,200.
pound tank fell on the victim, crushing his chest. He never regained consciousness, and died of the Injuries.
Investigation showed two years before, a similar Incident had occurred Involving another worker. The worker Involved had escaped with only a bad scare but the condition was not corrected.
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- .;'i "Your neglect could result In his broken neck' OE17264 Comanche Peak -Truck entering the parking lot struck a pedestrian, knocking him to the ground.
Luckily the person was not Injured. The pedestrian was walking In an open area and thought the driver had given him the right of way. However the driver of the truck did not see him. Has a near miss like this happened at PBNP?
7_'noring safety in any way may cause someone else to pay' OE17626 TMI -
During the disassembly of a RCP snubber a technician suffered the loss of the fingertip. A coworker shifted the position of the snubber cyrinder and did not realize the technician's finger was In the assembly.
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"Most obituaries would not be recorded if all close calls were reported' It happened at Prairie Island:
A year ago, somebody damaged one of the roll-up doors with a hydraulic lift. Unfortunately the employee failed to report this mishap and later the door fell narrowly missing another employee. This time we were lucky however the whole thing could have been avoided If only the damaged door were Identified and repaired.
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Point Beach Nuclear Plant Outage 1R28 DAY Supporting Operational Excellence I
Path N
Pt Picture Meets Ilral Outage Radiation Performance Donesn't Meet I
o-mm t ML-.
6£ 0Mwf This indicator measures cumulative dose radiation exposure and total number of personnel-contamination events (PCE ts > 5000 cpm) during refueling outages. The dose indicator is measured in Rem and individual PCE events.
Meets:
<=75 Rem Actual Cum.
Exceeds:
<=71 Rem Dose:
5.041 Rem Day 1 - Apnl 4.
Actual = 2.805 Cumulative = 5.041 Cumulative Forecast = 4.821 Meets: <=18 Exceeds: c= 12 Actual PCE's:
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Personnel Contamination Events Cummulative Dose Exposure I
20 18 16 14 12 10 8
6 4
2 0
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..Forecast Goal he110 0
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2 4
6 8
10 12 14 16 18 20 22 24 28 4-Actual
- - -Forecast
~GGoal 0 2 4 6 8 10121416182022242628303234
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.I Outage Status Report Plant:
Point Beach Unit I Day:
Tuesday Today's Date! Time:
4/06/04 /
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Industrial OSHA Recordables in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0
First Aid cases in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0
Significant near misses 0
Total for this outage 0
Summary:
No Injuries have been reported Radiological Dose outage to date 5.041 Projected to date 4.82i Outage Goal
<75 R Difference
+0.22 Number of PCEs 0
Summary a
Dose exceeds projections due to BMI project being ahead of schedule Nuclear Significant human performance errors and events in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I
Summary Personnel in Containment received a dose alarm while working under the wrong RWP Z.&
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N Mode:
ED Hot Standby (Mode 3)
E] Hot Shutdown (Mode 4) 0 Cold Shutdown (Mode 5)
El Refueling Shutdown (Mode 6)
RCS:
Temperature:
105 Pressure:
N2 Overpressure RV Level:
N/A Time to Boll:
110 Minutes Reactivity:
Green Core Cooling:
Yellow Power Availability:
Yellow Containment:
Green Inventory:
Green Spent Fuel Pool Cooling:
N/A There is no protected equipment uC6itic Pa aiCrit i'c) i Depressurized RCS Status of outage schedule:
12 Behind U Ahead 12 Hours Drained Pressurizer to 30%
ORT 3A Engineered Safeguards Test ORT 3B Engineered Safeguards Test Drain RCS to 70 % Rx Vessel Level S/G Man-way Platform Setup f
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Date Issue: -
1)DueDateC.; Responslbllity*
4/02/04 Incorporate Lessons Learned on Initial Downpower of XL-10 4//06/04 J.A. Schroeder 4/03/04 Resolve Blowdown Tank Leakage 4/06/04 Joe Krentz 4/04104 lP2A Charging Pump Troubleshooting 4/06/04 Mike Schug 4/06/04 Manipulator / Jib Crane Power SupBreaker 4
4/06/04 Joe Krentz
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u.AEDUpcoming Ma ormilestones,)tz-h.Schiduled
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- lji, Date' Time Date Time: -
_--Date Time Date Time Cooldown <200° 4/03/04 2100 4/03/04 2230 Heatup >2000 4/25/04 0900 Head Lift 4/09/04 09:00 InLtial 4/28/04 11:00 Refueled _
4/14/04 0300 On-Line 4/30/04 01:00 Page 1 of 1 4
Point Beach Nuclear Plant PBNP SHUTDOWN SAFETY ASSESSMENT AND FIRE CONDITION CHECKLIST OUTAGE SAFETY ASSESSMENT UNIT:
1 DATE:
April 6,2004 TIME:
0 KEY SAFETY FUNCiIONS:
REACTIVITY:
GREEN CORE COOLING:
YELLOW POWER AVAILABLE:
YELLOW INVENTORY:
GREEN CONTAINMENT:
GREEN SFP COOLING:
NA 300 PROTECTED EOUIPMENT:
COMMENTS:
Fire Protection Condition II RCS Time to Boil is >110 minutes ORT-3A Train A ESFAS Setup and Testing in Progress Iy 5
CommiffedtoNucdearExceilanco WIP IEY Point Beach Nuclear Plant U1R28 Operating Experience Tuesday, April 6, 2004 (for work Thursday, April 8, 2004)
OE subject:
OE16463 - Reactor Pressure Vessel Stud Tensioner Failure Results In Spraying Hydraulic Fuel In The Reactor Cavity
Purpose:
Provide a reminder that materials (tools) used in the cavity should be checked to ensure that thay have a low probability of contributing foreign material (will remain intact).
Why we chose this OE for today:
Reactor Head detentioning is scheduled for Thursday April 8", 2004.
Discussion:
During detensioning of the reactor pressure vessel head (RPV) the stud tensioner assembly failed resulting in spraying hydraulic fluid within the reactor cavity. The cause was less than adequate pre-outage preventive maintenance of the stud tensioner assembly. A more thorough PM program could have prevented the delay and additional work caused by this event during the outage.
==
Description:==
During detensioning of the RPV head, the stud tensioner assembly failed. The fitting between the high pressure hose at the pump and manifold on the strongback failed resulting in the high pressure hose blowing out of its fitting and spraying hydraulic fluid on the reactor pressure vessel head and flange. There was a concern that the loss of hydraulic fluid within the reactor cavity could have an adverse impact to safety related structural systems and components (SSCs) or to reactor water chemistry. Approximately 2.5 gallons of hydraulic oil (Mobile DTE 24) were lost when the hose fitting failed. An extensive cleanup of the RPV head removed all but trace amounts of the oil. An evaluation of the effects of the remaining oil on the RPV head was done and it was determined that the oil will have no adverse impact on the RPV head material (high strength, low alloy carbon
.steel). Trace amounts of oil remaining in the vessel flange area were reduced during flood-up by floating to the surface and being removed.
Causes: Inadequate preventive maintenance program for this tool.
Corrective Actions: Fitting between high-pressure hose at pump and manifold on strongback was replaced. The preventive maintenance requirements for the stud tensioners will be revised to strengthen evaluation requirements.
Safety Significance: The loss of hydraulic fluid within the reactor cavity was evaluated and considered to have no adverse impact to safety related SSCs or to reactor water chemistry. This could have also resulted in personnel injury had the hose impacted individuals working nearby Questions:
When were the hoses and fittings last checked?
How do we protect ourselves should a fitting fail?
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