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HLWYM HEmails

From: Albert WongSent: Friday, March 23, 2007 11:11 AMTo: George Adams; Fernando Ferrante; Tina Ghosh; Susan Cooper; Rosemary Reeves; Sheena

WhaleyCc: Robert Johnson (NMSS); Christopher RyderSubject: Re: Fwd: Revised Phase II sequence evalAttachments: Nuclear%20Services%20Brochure.pdf; NS-FS-0086_BWR Mast.pdf; Revised Phase II

sequence eval.txt

I found some additional information re: the PaR fuel handling equipment (FHE) interlocks and physical stop that can be relied on to prevent the fuel assembly from getting too close to the water surface: 1. The FHE is equipped with numerous limit switches/interlocks that will prevent the fuel from getting too close to the water or breaching the water surface when being moved around underwater. More importantly, the FHE has a built-in physical stop that limits the upward motion of the fuel arm to ensure there is sufficient water above the fuel. See picture D on page 5 of the first pdf file. The physical stop is located inside the casing roughly at the head level of the technician. 2. The second pdf file shows a BWR mast. This one is conceptually similar to one used by N. Anna (although N. Anna is a PWR plant). The mast protects the fuel from damage. At N. Anna, the fuel will be withdrawn into the mast during fuel movement, Once inside the mast, the mast limits the upward motion of the fuel. Based on (1) Chris' write-up, (2) Sheena's e-mail, and (3) ANSI 57.1 (page 8, section 6.3.4.1.5), I believe there is sufficient basis to screen out this event sequence unless there is strong evidence to retain this one. So, please speak up if you have a differering view. Otherwise, I propose we screen out this event sequence. Fernando - Can you make sure the rational why event sequence 2 (i.e., lift height of a fuel assembly is exceeded) is screened out is clearly documented in section 2.3.2 (Screened out Events and Hazards), please? Thanks Albert >>> Sheena Whaley 03/20/2007 11:14 AM >>> Since we don't have detailed design information, to fill in the gaps, I thought we agreed to conceptualize based upon other standard operating SFPs. If we do that then based upon what Chris wrote (and even Jim's conclusion) this can be screened out. Also, I don't think we've found any recent events that show that this has ever happened. Sheena >>> Albert Wong 3/20/2007 11:02 AM >>> Attached is Jim Pearson's comments re: event sequence 2 (over-withdraw the fuel assembly too close to the water surface). FYI. >>> James Pearson 03/20/2007 9:46 AM >>> Albert, My comments are attached. Hope they are helpful. Jim >>> Albert Wong 3/14/2007 5:19 PM >>>

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Jim - When you return to office, can you take a quick look at the 2nd sequence in the attached file from Chris, please? He believes that sequence can be screened out because of the admin and eng. systems in place. What you think? As always, thanks for your help, Albert >>> Christopher Ryder 03/14/2007 3:21 PM >>> Albert, The number you cited, 10e-2, should be 10e2, I fixed this. I added a reference to Table 2. You should send it to team members. Chris

Hearing Identifier: HLW_YuccaMountain_Hold_EX Email Number: 36 Mail Envelope Properties (Albert.Wong@nrc.gov20070323111104) Subject: Re: Fwd: Revised Phase II sequence eval Sent Date: 3/23/2007 11:11:04 AM Received Date: 3/23/2007 11:11:04 AM From: Albert Wong Created By: Albert.Wong@nrc.gov Recipients: "Robert Johnson (NMSS)" <Robert.Johnson@nrc.gov> Tracking Status: None "Christopher Ryder" <Christopher.Ryder@nrc.gov> Tracking Status: None "George Adams" <gadams@cnwra.swri.edu> Tracking Status: None "Fernando Ferrante" <fferrante@cnwra.swri.edu> Tracking Status: None "Tina Ghosh" <Tina.Ghosh@nrc.gov> Tracking Status: None "Susan Cooper" <Susan.Cooper@nrc.gov> Tracking Status: None "Rosemary Reeves" <Rosemary.Reeves@nrc.gov> Tracking Status: None "Sheena Whaley" <Sheena.Whaley@nrc.gov> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 2780 3/23/2007 11:11:04 AM Nuclear%20Services%20Brochure.pdf 975504 NS-FS-0086_BWR Mast.pdf 256288 Revised Phase II sequence eval.txt 75283 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:

“Automating the Reach of the Nuclear World”

NUCLEARSERVICES

GROUP

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GraphicalControls

Speed YourFuel Handling

Refueling equipmentcontrollers are our

specialty. We've adapted andrefined the application ofcomputer technology forcontrolling nuclear fuelhandling equipment in ourFuel Net™ controllers. Theseadvanced controllers aredesigned specifically for theneeds of refueling operatorsat your plant. Up to three axesof motion—bridge, trolley andhoist—can be simultaneouslyoperated. The systemautomatically checks forboundary zones, load weightsand machine interlocks while

executing a safe, quick travelpath. We also provide asimulator/ tester that links tothe refueling machinecontroller. The simulator/tester can be used forpreoperational console check-out and to train operatorsprior to an outage.

In automatic mode, apreprogrammed fuel

movement sequence isdownloaded into the Fuel Net.The operator simply initiatesthe execution of thepreprogrammed steps. Fuelbundle movements are

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monitored on screen by theoperator with both aninteractive graphical interfaceand remote video cameradisplay. The automatic modehelps eliminate the potentialfor operator error andsignificantly improves bundletransfer times. There's also asemi-automatic and manualmode of operation. Onceyou've seen how easy andfast the Fuel Net is, you'llunderstand why it's the mostwidely installed replacementcontroller for refuelingequipment in the world.Utilities who have installed the

Fuel Net replacementcontroller have often savedenough critical path time torecover the cost of thecontroller during the first fulloutage of use.

Call us to arrange an on-site demonstration to see

just how much the Fuel Netcan cut your outage time.

A Fuel Net controller with remotecamera inset.

B Mast hoisting screen showingmast vertical travel, load limitsand interlocks.

C Core area screen showing thecoordinates of the mast and thedestination location.

D Screen showing path betweenthe upender and the reactorcore.

E Fuel Net installed on aEuropean BWR Refuelingmachine

F Fuel Net operating during anoutage.

B C D

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We CanUpgrade YourEquipment To

PerformBetter Than

New

Take advantage of ourexperience in nuclear

power plants all over theworld to modify and upgradethe mechanics of yourequipment. We can designand manufacture the upgradeof any component on any fuelhandling equipment. We'vemade improvements totelescoping masts, hoistequipment, mast mountedunderwater camera systems,cable and hose handlingsystems and replacedgrapples for both PWR &BWR fuel.

On transfer systems, we'vemade substantial

improvements to upender andtransfer cart drives, anddesigned advanced load andposition monitoring systems.We can also supply manualand electrically poweredauxiliary work platforms.

If you need to upgrade polaror reactor building cranes—

we can do it. We start with athorough inspection of yourservice cranes and thenprovide you with a prioritizedrepair and upgrade list. We'lltell you both what the upgrade

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will cost and what kind ofreturn you can expect inperformance and reliability. Wecan provide renovation of loadweighing systems, bridge andtrolley position monitoring andboundary zone systems. Oneof our most popular craneupgrades is variable speeddrive control systems forbridge, trolley and hoistfunctions. These variablespeed drive controls providesmooth travel with very precisecontrol thus reducing the timerequired to execute your heavylifts.

Find out more about any orall of the equipment and

services we offer bycontacting us. Making yourequipment perform better thanwhen it was new is always ourobjective. We'll discuss yoursituation and makerecommendations on the bestcourse of action to shortenyour outage.

A New transfer system upenderand cart being assembled andtested at PaR's facility.

B New BWR grapple with an inte-gral zoom camera lens.

C Fuel Net controller on a SpentFuel Handling Machine.

D PaR technicians verifying con-sole installation.

E Communication reel on a bridgeis an accessory to an upgradedconsole.

F Dual encoders installed on a trol-ley provide position input to con-sole.

G European BWR grapple engagedon a fuel bundle.

B C

E

F

G

D

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Move YourFuel More

Reliably,Faster &

Safer

How can we make it morereliable and still move fuel

faster? That question isconstantly asked of us. Ouranswers have led us to beingthe world's leading supplier offuel handling equipment forthe nuclear power industry.Our approach to problem-solving is the key to oursuccess. We look beyond thestandard solutions, often towhat other industries aredoing to solve similarproblems. This approach hashelped us introduce manyfirsts in the nuclear powerindustry. We have premiered

microcomputer basedreplacement controllers fortransfer systems, refueling andspent fuel handling machines,all integrated to communicatewith each other.

PaR Systems begandesigning and manu-

facturing complete fuelhandling systems in 1968.Since then, over 80 nuclearpower plants in eightcountries have benefited fromPaR technology. Today, wespecialize in replacement fuelhandling equipment, for bothPWR and BWR plants.

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Working with a utility's staff,we will analyze and providerecommendations to speedfuel movement, improvereliability and safety, oftenwith a cost payback withinone outage.

Upgrades vary from asimple replacement cable

reel to a complete new fuelhandling machine. Our highlyexperienced mechanical,electrical and softwareengineering groups ensureyour equipment will bedesigned for speed, precisionand customized for thespecifics of your plant. All

equipment is assembled andfully tested in our 87,000 ft2

(8,100 m2) facility. Eventelescoping masts are fullytested in our specialized high-bay test area.

On-site technical support isprovided to help install

and test new equipment andtrain your personnel. We'realso there during your outage,to insure your equipmentperforms efficiently andreliably. Our experiencedtechnical support staff hasbeen a hallmark at PaRSystems since 1961.

A A supervisor, using theSimulator/Tester in the fore-ground, helps train an operatorby creating fuel handling situa-tions on the refueling machineconsole in the background.

B Mechanical engineer designingat an advanced CAD station.

C One of PaR's software engineersdeveloping a custom control pro-gram.

D Control room console showsreactor operators real-time fuelmovement information.

E Final wiring of a control console.

F On-site technical support isavailable from PaR prior to andduring an outage.

G PaR's high-bay test area provid-ing 84 feet (25 m) of vertical testcapability.

B C

E F

D

G

We're YourFuel HandlingEquipment &

ServiceSpecialists

• Complete New Refueling Equipment

• Refueling Equipment Modifications

Controls

Mechanical

• Service Crane Upgrades

• Installation Services

• Outage Technical Support

PaR Systems, Inc. • 899 Highway 96 West • St. Paul, MN 55126 U.S.A.Phone: (651) 484-7261 • Fax: (651) 483-2689

www.par.com or nuclear@par.comCertified to ISO 9001

Printed in U.S.A.© 2000 PaR Systems, Inc.

BackgroundThe new FuelMaster BWR mast designed byPaR, a subsidiary of Westinghouse, is a free-floating, free-swinging, telescoping mastdeveloped as a replacement mast on existingU.S.-style BWR refueling and fuel-handlingplatforms. Made of 304 stainless steel tubing,the mast is a square, tubular design with onestationary section and three moving sections.

PaR Nuclear designed this mast with the fol-lowing objectives in mind: simplicity, ease ofmaintenance, interchangeability of compo-nents, and suitable clearances to prevent bind-ing and crud traps.

Description

The FuelMaster mast is a gimbal-mounted design that iscompatible with both PaR Nuclear and Sterns-Roger plat-forms. The gimbal design contains a spring system fordamping impact forces on the mast in the vertical direc-tion. The lower section of the mast also accommodatesgrapples that fit other PaR Nuclear masts, NF400 masts,and NF500 masts. It easily connects to the grapple limitswitch, lighting cable, grapple cylinder pneumatic plumb-ing, and grapple camera.

The square geometry of the mast design is stronger inbending than an equivalent sized diameter circular mastdue to its higher moments of inertia about the X and Y axes (horizontal centerlines).

TestingDuring the design phase, PaR Nuclear engineering com-pleted mast structural analysis using a solid model andfinite-element analysis. These tests were conducted inTaiwan at a training facility under real-life conditions for

Nuclear Services

For more information, call your local Westinghouse Electric Company sales representative.

FieldServices

FuelMaster® BWR Mast

(Continued on back)

six weeks. During the testing, the mast was removed andinspected repeatedly for wear and no noticeable wear ofthe guides was observed. The mast functioned flawlesslyover a full count of 16,000 plus cycles. Depending uponthe size of a specific core, that cycle count would bebetween 8 and 12 refueling outages.

Verified PropertiesThese calculations verified the structural integrity of thenew BWR square mast when subjected to several worst-case scenario dynamic loadings. The analysis proved themast will withstand a section drop of any of the movingtubes, and will not yield during high speed simultaneousbridge, trolley, and hoist operations of 62, 40, and 50 fpm,respectively.

The mast bearings between the mast tube sections arewear strips made of Delrin®. Delrin is a plastic materialthat is impact resistant, strong, stiff, dimensionally stable,wear and fatigue resistant, easily machineable, and chem-ical and moisture resistant. It is also low in friction, andhas a wide temperature range.

Benefits

• Square geometry of the mast design is stronger inbending.

• Components are easily interchangeable.

• Mast bearings made of Delrin are: impact resistant; strong; stiff; dimensionally stable; wear, fatigue, chemical, and moisture resistant; and machineable

For additional information, please contact:John QualizzaVice President, Business DevelopmentPaR Nuclear Inc.899 Highway 96 WestShoreview, MN 55126651.528.5282

Westinghouse Electric CompanyBox 355Pittsburgh, PA 15230

www.westinghousenuclear.comApril 2006

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