ML20050F892

Requests Authorization to Obtain Design Data from GE for Use in Establishing Ref Plant Data Base for BWR/4 Plants.List of Requirements Encl

ML20050F892
Person / Time
Site:	Browns Ferry
Issue date:	03/23/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Parris H TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8204130485
Download: ML20050F892 (27)

Text

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~5 Docket Nos. 50-259 Docket File Nw.Mk.

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50-260 NRC PDR O

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1 50-296 Local PDR

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ORB #2 Rdg D. Eisenhut 0 ELD i

Mr. Hugh G. Parris 0I&E (1)

Manager of Power R. Clark Tennessee Valley Authority W. Hodges w/ copy of letter only 500 A Chestnut Street. Tower II SNorris Chattanooga, Tennessee 37401 NSIC ACRS (10)

Dear Mr. Parris:

J eltemeg

SUBJECT:

REQUEST FOR RELEASE OF DATA FOR TRAC CODf BWR/4 MODELING RE: Browns Ferry Nuclear Plant, Units 1, 2 and 3 The purpose of this letter is to request the Tennessee Valley Authority to authorize the General Electric Company (GE) to release Browns Ferry Nuclear Station design data to the NRC for use in establishing a reference plant data base for BWR/4 plants. Establishment of such a data base for each of the BWR/4, 5, 6 product lines is an important part of our effort to implement the TRAC computer code for BWR transient and accident analyses.

While the bulk of our needs can be acquired on a generic basis from GE, some plant specific data will be required to complete a data package for each product line. A list of requirements has been developed by our con-tractor, EG&G (Idaho), and is enclosed. He note that some of the data needs i

are in areas outside the scope of GE. Therefore, we request a meeting at your earliest convenience, between our contractor personnel and members of the TVA engineering staff at which time the specific areas in the enclosure that we need your assistance with will be identified. We believe that EG&G can accomplish its objective at your site in less than one week. If further clarification of our request is required you should contact Gary Wilson, INEL, FTS 8-583-9511.

This information request is not related in any way to any safety review of the Browns Ferry Huclear Plant. Your consideration of the request is greatly appreciated.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, CRIG13AL SIGED M Domenic B. Vassallo, Chie Operatino Reactors Branch #

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As stated 8204130485 820323 PDR ADOCK 05000259 FFICIAL RECORD COPY us= =-mm NRC F, P

PDR

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j Mr. Hugh G. Parris-cc:

H. S. Sanger, Jr., Esquire General Counsel Tennessee Valley Authority 400 Commerce Avenue E 11B 33 C Knoxville, Tennessee 37902 Mr. Ron Rogers Tennessee Valley Authority 400. Chestnut Street, Tower II Chattanooga, Tennessee 37401 Mr. H. N. Culver 249A HBD 400 Commerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902

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Robert F. Sullivan U. S. Nuclear Regulatory Commission Route 2 Box 311 Athens, Alabama 35611 Athens Public Library South and Forrest Athens, Alabama 35611 Mr. John F. Cox Tennessee Valley Authority W9-D 207C 400 Commerce Avenue Knoxville, Tennessee 37902 Mr. Herbert Abercrombie

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Tennessee Valley Authority P. O. Box 2000 Decatur, Alabana 35602 James P. O'Reilly Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 l

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ATTACHMENT 1

-(

! ; FORMATION REQUIRED TO CONSTRUCT A TRAC--BD1 MODEL CF A kWR PLANT Information is requested in the following format:

Recirculation loops Steam Lines feedwater System Vessel Lower Plenum Control Rod Guide Tubes Core Region Core Bypass Region Upper Mixing Plenum Standpipes Steam Separators Steam Dryers Steam Dome Downcomer

~

Auxiliary Systems HPCI LPCI/RHR Core Spray RCIC SLCS Balance of Plant Piping from Exterior Isolation valve to Outboard MSIV High and Low Pressure Feed Heaters feed and Condensate Pumps Demineralizers Condensor Turbine o

O O

Primary Cootainment Reactor Btfilding Drywall Suppression' Pool Control Systems 0

9

.e 9

\\

A e

a e

D 1

S 9

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RECIRCULATION LOOPS 1.

Flow area along flow path (including jet pumps)

~

2.

Diameter along flow path f

3.

Loss coefficients along flow path 4.

Elevations along flow paths 5.

Piping geometry and material along flow path s

6.

Normal operating thermal-hydraulic initial conditions 7.

Location and size of penetrations 8.

. Valve locations, resistances, flow geometries, behavior during normal operation during transients, and cycling times 9.

Jet pump M and N ratio characteristics

10. Recirculation pump geometry data Pump volume Effective pump volume flow area Effective pump volume hydraulic diameter Pump yolume flow length

'.~.

Pump volume height Pump volume elevation 4

e o

e

'.. w.

^ -~ '

u.~.... ~.

.. w w.:.,n pump and pump motor moment of inertias pump motor torque vs. pump motor speed table pump frictional torque ccefficients as a function of pump angular velocity maximum forw'ard and reverse pump rotational velocities Single phase homologous pump data c.

1 Data tables of the independent variables vs. each dependent variable with definition of terms in variables given in Table 1:

i PUMP HOM0LOGOUS CURVE DEFINITIONS TABLE 1.

Dependent Variable Regime Regime Mode Independent Number 10 Name a

y v/a_

Variable Head _

Toraue 1

HAN Normal

>0

>0

< 1 v/a h/m2 Sf,2 2

HVN Pump

>0

>0

> 1 a/v h/v2 g/y2 3

HAD Energy

>0 70

> -1 v/a h/a2 s/a2 2

gfy2 4

HVD Dissipation

>0

<0

< -1 a/v h/v 2

2 S/a 5

HAT Normal

<0

<0

< l v/a h/a 2

2 6

HVT Turbine

<0

<0

> 1 a/v h/v s/v2 2

s/a 7

HAR Reverse

<0

>0

> -1 v/a h/a 2

afy2 8

HVR Pump

>0

< -1 a/v h/v Rotational velocity ratio (actual rotational velocity / rated a

=

rotational velocity).

Volumetric flow ratio (actual volumetric flow / rated volumetric y

=

flow).

Head ratio (actual head / rated head).

h

=

Torque ratio (actual torque / rate torque).

8

=

Four quadrant curves (required only if single phase homologous curves above are not available):

i l

~

w=

w. ~. - w A.u..

Pu.sp inlet (suction) flow area hydraulic diameter elevation forward ficw energy loss coefficient reverse flow energy loss coefficient Pump outlet (discharge) ficw area hydraulic diameter elevation forward flow energy loss coefficient reverse flow energy loss coefficient

11. Recirculation Pump Performance Data a.

General rated angular velocity rated volumetric flow rated head rated pump torque rated pump motor torque rated density b.

Operating parameters for normal steady state at 100% rated plant conditions angular velocity volumetric flow head pump torque pump motor torque density

h;

. -.~.a.' usSu.GineLLCMic e

i

...r.

' Data tables (or plots if data are not availaole) describing the pump characteristics in terms of:

volumetric flow rational velocity head d.

Two phase pump data 1.

Fully degraded two phase homologous pump data (consisting of 16 data tables in the same format as that described for single phase) with a specific correlation between void fraction and two phase head and torque relative to single phase head and torque 2.

If the above data are not available, provide any available two phase pump data and related correlation (s) with complete explanatory information Thermalhydraulic plant conditions (for normal steady state at e.

100% rated pcwer) 1.

Pump volume a.

average pressure b.

average temperature c.

average quality 2.

Pump suction and discharge junctions a.

mass flow f.

Control logic Require all trip setpoints, logic and interlocks associated with I

the tripping off of each pump l

. ; = ;;p;;

s..

.,.. L -. a u a _ u s u i:J:h, C u.i... L c :r..

STEAMLINES 1.

Same as Items 1 through 7 for the recirculation loops

~ 2.

Geometry and resistance of flow restrictor 3.-

MSIV Closure times Causes of trips 4

Steam relief valves Number and locations of valves

' Valve diameters Valve flow vs. pressure (opening and closing modes)

. Valve setpoints Relief valve sink volume S.

ADS Same information as for MSIV and relief valves

+

6.

Turbine stop valves Same information as for MSIV and relief valves t

4 7.

Pressure control valves 4

I Same information as for MSIV and relief valves l

8.

Turbine bypass valves Same information as for MSIV and relief valves v

i 9

E"

.:_e :2.2.<. ?. _.. _ L __

t_..

FEENATER SYSTEM

~

1.

?! umber of primary containment and vessel penetrations for feedwater lines 2.

Same as Items 1 through 8 for the recirculation loops 3.

Control logic for feedwater system 4

I e

o.

L.

. : iaDL RJ l

- ' ' vesstL' Lower Plenum (Below Jet Pump Outlet) 4 l.

Flow area as a function of elevation 2.

Total water volume (excluding that in guide tubes) 4 3.

Total metal volume including guide tubes 4

Composition of internal structural materials k

5.

Forward and reverse flow loss coefficients 6.

Hydraulic diameter as a function of elevation 7.

Nominal steady state hydraulic initial conditions 8.

Geometry and composition of vessel head 9.

Insulation Control Rod Guide Tubes 1.

Number of tubes 2.

Inside flow area and hydraulic diameter as a function of elevation 3.

Flow area and hydralic diameter (not at grid spacer) 4 Elevations of lower and upper tie plate, bottom and top of active fuel 5.

. Number of. grid spacers per bundle l

6.

Center line elevations of grid' spacers i

e e

e O

N r

e-

m:.:

.~.;A.~iu w;,,,a,..

-..a 7.

Minimum flow area and forward and reverse loss coefficients at grid spacer, core. inlet orifice, upper tie plate 8.

Core support plate composition, thickness, elevation, volume and surface area 9.

Nominal initial thermal hydraulic pressures temperatures, void fractions for peripheral, average, and high power bundles.

l

10. Nominal core power axial, radial, and local distributions Reactor protective systems and engineered safety features 11.

interactions with core

12. Reactor kinetics--beginning of life Scram rod reactivity insertion as a function of time for:

a.

1.

all rods insert 2.

all but most reactive rod insert I

b.

Reactivity change as a function of moderator density Density reactivity change as a function of boron c.

concentration d.

Reactivity change as a function of fuel temperature (Doppler)

Baron worth as a function of boron concentration and e.

moderator temperature

13.. Reactor kinetics--end of life Scram rod reactivity insertion as a function of time for:

a.

1.

all rods insert 2.

all but most reactive-rod insert

.e.

~a...s.a.w = _ - :: -wrum u 2-.

b.

Reactivity change as a function of moderator density

~

c.

Density reactivity change as a function of boron concentration d.

Reactivity change as a function of fuel temperature (Doppler)

14. Fuel rod pellet data a.

Composition

\\

b.

Enrichment (s) c.

Cold state temperature for fuel dimensions d.

Density 1

e.

Fuel pellet height j

f.

Diameter 9

Pellet dish spherical radius h.

Pellet dish depth I

i.

Pellet dish diameter J.

Burnup at end of each cycle k.

Fuel sintering temperature i

1.

0/M ratio l

i m.

Fuel surface roughness l

O e

l l

=:.,32 &::...u a..x x.

w Radial power cistribution across pellet such that n.

n(rf)-rf),]

N P n=1 2

't where radius to outside of fuel pellet r

=

f th inner radial coordinate of n mesh spacing

=

rn h

outer radial coordinate of n mesh spacing

=

r +1 n

th mesh spacing power profile factor for n P

=

n number of mesh spacings in fuel N

=

l

15. Fuel rod data a.

Fuel stack height b.

Fuel stack insulating pellets 1.

composition 2.

length a.

top pellet b.

bottom pellet Upper plenum volume including spring c.

d.

Plenum spring 1.

composition 2.

number of coils 1

I 3.

uncompressed height.

i' a

4 4.

j-i

4 uncompressed outer diameter 5.

spring wire diameter e.

Fill gas composition

.f.

Fill gas pressure at cold state g.

Fill gas temperature at cold state h.

Fuel rod cladding 1.

composition 2.

inside diameter 3.

outside diameter 4

fuel rod length 5.

arithmetic mean roughness i.

Axially averaged and time averaged fast neutron flux cladding exposed to during lifetime.

Fast neutron lower threshold is 1 Mev.

j.

Axially averaged and time averaged thermal neutron flux cladding exposed to during lifetime k.

Time span of cladding neutron exposure 1.

Fuel rod pitch

16. Fuel rod / assembly thermalhydraulic data Hydraulic diameter, nominal channel a.

b.

Rod average linear heat rate Peak to average heat flux factors as a function of axial c.

elevation e

D 5

e e

m 9

. - ~... -

c-_.,w m _,....n;,,.

a d.

Hot channel and hot spot parameters 1.

maximum heat flux 2.

maximum linear heat rate 3.

fuel maximum temperature 4

cladding maximum temperature 5.

hot channel outlet temperature 6.

hot channel outlet enthalpy 7.

DNB ratio (W-3 correlation), steady state Core Bypass Region 1.

Flow area, volume, hydraulic diameter 2.

Top and bottom elevations Percentage bypass of core full power flow and description of 3.

individual bypass paths and flows 4.

Core shroud 10, 00, composition 5.

Control rod geometry, surf ace area, volume, and composition Volume and surface areas of other structures in the bypass region.

6.

7.

Minimum flow area and loss coefficients Steam Separation and Mixing Plenum Region 1.

Elevation of bottom and top of top guide 2.

Flow area and loss _ coefficients for top guide i

3.

Fluid' volume, flow area, and hydraulic diameter of mixing plenum 4.

Head shroud elevations, geometry, and composition

(.

e e

l

bis a.a

a. mm',szu.,

5.

Nominal initial pressures, temperatures, and void fractions of the mixing plenum Standpipes 1.

Number of pipes, elevation, and average length 2.

Flow area and hydraulic diameter per pipe i-

, 3.

Standpipe ID, 00, composition

' Nominal initial fluid temperature, pressure, flow rate and void 4.

fraction in standpipes Steam Separators 1.

Number of separators 2.

Volume and top and bottom elevations 3.

Flow areas (axial, radia'1, and azimuthal) as a function of J

elevation I

4 Metal surface area, volume, composition, 10, 00 t

5.

Form loss coefficients 4

6.

Recirculation flow as a function of key parameters t

7.

Nominal flow rate, void fraction,-pressures and fluid temperature in each separator Carryunder/ carryover behavior within plant operating envelope 8.

l l

I

~

g

+e-4s o

g----

g

a. aa uw-a-L..:. m.

L.

Steam Dryers l.

Number of dryers Volume, top and bottom elevations and flow area as a function of 2.

elevation 3.

Metal surface area, volume, composition 4

Form loss coefficients

5.

• Recirculation flow as a function of key parameters Nominal flow rate, void fraction, pressures, and fluid 6.

temperature in each dryer, Steam Dome Elevations of top of steam dryer, top (inside) of upper head, and f

1.

steam line nozzle centerlines.

Radius of curvature, thickness, and composition of upper head 2.

3.

Fluid volume Flow area and hydraulic diameter as a function of-elevation 4.

Nominal flow rate, void fraction, pressures, and temperatures 3.

1 6.

Form loss coefficients I

i Internal (if any) metal volume, heat transfer area, and 7.

l i

composition.

l l

8.

Insulation I

e i

l L

4 W

G 4

e

7,

..,s. ~.w.

. s =-

. Dcwncoh.2r (Betwnn Too of Steam Separator and Shroud Support Plate) 1.

Vessel ID, 00, composition, insulation _

2.

Core shroud ID, 00, and composition vs. elevation 3.

Jet pump wall thickness and composition as a function of elevation 4

Miscellaneous metal volumes and heat transfer areas (excludes vessel wall, shroud, standpipes, and steam ;eparators and dryers).

5.

~ Flow area and hyradulic diameter as a function of elevation 6.

Feedwater sparger elevation, number of nozzles 4

-7.

Feedwater nozzle geometry, form loss coefficients, flow distribution data 8.

Nominal pressures, temperatures, flow rates, and void fractions as a function of elevation.

e i

I I

4>

0 4

e O

G 98 8E>

m

- - p m

4_.,....----

,, ;_2w_g,

.... 2 _m. _

^

AUXiLfARY SYSTEMS HPCI 1.

14 umber of pumps 2.

Electrically or turbine driven power source?

3.

Available suction reservoir volume, pressure, temperature 4

Operational setpoints 5.

Injection locations 6.

Injected flow rate and temperature as a function of pressure and number.of pumps 7.

Heaters or coolers?

8.

Spray distribution data LPCI/RHR (Same information as for HPCI)

Core Spray (Same inforn.ation as for HPCI)

RCIC (Same information as for HPCI)

SLCS 1.

Tank volume, boron concentration 4

u, i.., ~...... -..:. ~ : : a a c.:......

2.

Pump performance sp cification j

3.

Logic of operation 0

0 6

e e

9 9

w.

+-.

L...

• w:-

. = -., _ --

~

BALANCE OF PLANT Piping from Exterior Isolation Valve to Outboard MSIV l.

-Flcw area, diameter, elevations and loss coefficients along flow path 2.

Piping geometry and, material 3.

Penetrations and alternate connections 4

Nominal thermal hydraulic conditions 5.

Valve locations, geometries, flow resistances, behavior during transients High and low Pressure Feedwater Heaters 1.

Number and geometry of heaters 2.

Nominal primary and secondary side flow rates, pressures, temperatures Feedwater, Condensate, and Condensate Booster Pumps (Same information as listed for recirculation pumps)

Demineralizers 1.

Number, geometries and flow resistances 2.

Nominal flows, pressures, temperatures, and. levels j

Condensor Geometry and nominal flows, pressures, temperatures,.and levels d

i

u-..,.~ =a.u

.,.L2-W L,_,

~

Turbine

.r Geometry, performance characteristics, nominal conditions m,

we,-

+m m -<awmo e '9 o m4 "6 9

• ** *~ *

• ~'

~ ^

^

~

. 4 ;. w.a__,

._,sm262s PRIMARY CONTAINMENT Drywell 1.

Net free volume 2.

Wall dimensions and composition Internal heat structure volume, surface, area, and composition 3.

4.

Nominal operating pressure, temperature, and humidity

- 5.

Top and bottom elevations

6. -Containment isolation sequences, logic Suppression Pool _

Suppression pool dimenstions, volumes, flow areas, elevations i

1.

2.

Nominal thermal hydraulic conditions 1

1 f

s.:. -

+ w ~_= ~, ~.!.

CONTROL SYSTEM CHARACTERISTICS Assuming the control systems used in the BWR plants can be described by an equation similar to:

2j

+ K /Edt AV = K E + K 3

j

- where variable v

=

deviation from desired value of V E

=

proportional constant K

=

j derivative constant K

=

2 reset constant K

=

3 The exact form of the equations and the magnitude of each constant are needed for the feedwater, recirculation and the pressure regulation systems as well as the turbine stop and bypass valves. Other specifics needed for each-control system are:

1.

The time lag between the signal generation and system response.

2.

Control system instrumentation type, location, sensor location, time response, accuracy, ranges, power supplies, and readouts in the control room, 3.

A control block diagram for each system showing the relationship s

between the components of each system and the systems to one another.

e m

e M

M e-

V l

This information is recuired for level, pressure, and core flow control systems. Also required are all operational and emergency setpoints, delay times, and trip logic.

4 4

s O

e a

e 6

h

..