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Forwards Proposed Changes to FSAR Re Dry Active Waste Facilities,Alternate Radwaste Bldg (Arb),Control Area Mod & ARB Bridge Crane Addition
	ML20151Q711
Person / Time
Site:	Vogtle
Issue date:	08/01/1988
From:	Bailey J; GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	GN-1472, NUDOCS 8808110263
	Download: ML20151Q711 (77)
	v • d • e

2 Georgia FDwer Company F0st Ofhce Box 282 i o' Wrrnesboro, Georgia 30830 l Telephone 404 554-9961 404 724-8114 Southern Company Services, Inc Post Ofhce Box 2625 B:rmingham, Alabama 35202 w phome20sa' " "

Vogtle Project l

August J. 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk File: X7dC35 Washington, D. C. 20555 Log: G'.- 1472 PLANT V0GTLE - UNITS 1 & 2 !

NRC 00CKETS 50-424, 50-425 OPERATING LICENSE NPF-68, CONSTRUCTION PERMIT CPPR-109 ;

FSAR CHANGES FQ.( RADWASTE FACILITIES I Gentlemen:

Attached are the proposed changes to the FSAR for the Dry Active Waste (DAW) Facilities, Alternate Radwaste Building (ARB), Control Area modification, and the ARB bridge crane addition. Existing warehouses located on the southwest portion of the owner controlled area are being extensively modified to handle the DAW. A new addition to the ARB will house the ARB Control Room and dress-out area. The existing pedestal crane in the ARB is being replaced by a bridge crane.

In our letter, GN-1461 dated June 14, 1988, to the NRC Staff, reference was made to the fact that a subsequent submittal would contain the information concerning the DAW Facilities and the ARB Control Area modi fication. This letter provides the promised information. Should you have any questions concerning these proposed FSAR changes, please inquire.

Sincerely, k-J. A. Bailey Project Licensing Manager JAB /sem xc: NRC Regional Administrator J. E. Joiner, Esquire NRC Resident Inspector J. B. Hopkins (2)

W. G. Hairston, III G. Bockhold P. D. Rice R. J. Goddard, Esquire J. P. Kane R. W. McManus R. A. Thomas Vogtle Project File B. W. Churchill, Esquire GO

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LIST OF FIGURES'(Continued) 1.2.2-34 Radwaste Solidification Building Equipment Location Layouti Level A el 192 ft 0 in. to 220 ft 0 in.;

i Level 1 el 220 ft O in. to 246 ft 0 in.; Level 2 el 246 ft 0 in, and Above 1.7.1-1 Legend for Electrical Drawings 1.7.1-2 Legend for Control Logic Drawings 1.7.1-3 J Legend for Control Loop Drawings 1.7.1-4 Legend for Communications and Lighting Drawings 1.7.2-1 P&ID Inctrumentation Identification and Symbol: .

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VEGP-FSAR-1 1

1 1.2.2 FACILITY APRANGEMENT The principal buildings and structures associated with the plant include the containments, the equipment buildings, the turbine building, the auxiliary building, the control building, a

the diesel generator buildings, the auxiliary feedwater pumphouses, the fuel handling buildings, the radwaste solidification and transfer buildings, the nuclear service

~ cooling water towers, and the circulating water cooling towers.

Anc!Llary structures include the administration building, warenc.use building and receiving facility, service building, a maintenance building, plant entry and security building, vehicle .-.intenance facility, intake and outfall structuras, boathouse, chlorination facilities, fire pumphouse, demineralizer building, ield support building, the nuclear trainingfacilitN.,a.*/ssalternate da y un m radwaste buildingj g au/ lIl25 g

These buildings and structures are founded upon suitable p material for their intended application. Structures essential to the safe operation and shutdown of the plant are designed to withstand more extreme loading conditions than normally considered in conventional nonnuclear design practice. The safety-related buildings and their internal structures are l

designed to provide protection as required frem floods, tornadoes, earthquakes, and the failure of equipment producing flooding, missiles, and pipe breaks. Additional discussion of design considerations is provided in chapter 3.

l Location in figure 1.2.2-1.

and orientation of the buildings on the site are shown The general arrangement of the power block buildings is shown in figures 1.2.2-3 through 1.2.2-14.

Equipment locations for Unit 1 are also shown in figures 1.2.2-15 through 1.2.2-34.

The containment, shown schematically in figures 1.2.2-31 and 1.2.2-32, encloses the reactor coolant system, the steam i

generators, some of the engineered safety features systems, and

! supporting systems. The functional design basis of the Seismic l Category 1 containment, including its penetrations and isolation valves, is to contain with adequate design margin the-energy released from a design basis, high energy line break accident and to provide a leaktight barrier against the uncontrolled release of radioactivity to the environment, even assuming the loss of one of the two trains of engineered safety features. The containment is a prestressed, post-tensioned, reinforced concrete, right circular cylinder with a hemispherical dome.

The equipnient building, shown in figures 1.2.2-l' and 1.2.2-18, provides protection from the weather for equipment locat9d within the building. The equipment building consists of 1.2.2-1 Amend. 25 9/86 l

e VEGP-FSAR-1 t i

The radwaste solidification system is housed within two buildings connected by a subterranean tunnel. A small transfer building, adjacent to the auxiliary building (figure 1.2.2-33),

serves as a collection tankage area, providing waste holdup and pumping capacity necessary to transport the liquid and slurry wastes to the remote solidification building. The underground tunnel routes the process piping from the auxiliary building to

, the transfer building and from the latter to the solidification building. Shown in figure 1.2.2-34, the radwaste solidification building is a reinforced concrete structure designed to the seismic requirements of Regulatory Guide 1.143.

It contains receiving tankage for the liquid and slurry wastes, volume reduction and solidification equipment, and a solidified waste drum storage area. The solidification system processes #

liquid and solid radioactive wastes generated by the plant as well as the residue from the volume reduction system.

The alternate radwaste building, shown in figure 1.2.2-35, is a metal siding building supported on a base slab with a "lean-to" structure on the north side for storage. The building basemat is designed with curbing to retain radioactive liquid in the event of an operating basis earthquake per Regulatory Guide 1.143. It contains a domineralizer vault, laydown area, and a truck-trailer loading bay. Areas have been allotted to stage dry u::t; mae;;t.., ;..J" -

processshields,bprocessskids,1 f-- @ ; m M. ,,,(

f Th(eWsitr D water cooling tower is a concrete, circclating natural draft, hyperbolic structure. The tower is designed to '

dissipate all excess heat removed from the main condensers and i accomplishes this function by the use of the spray network, the l

tower basin, and circulating water pumps, piping, and valves.

The intake structure houses the circul'ating water pumps, l turbine plant cooling water pumps, and associated auxiliary equipment and piping.

i The nuclear service cooling water towers, shown in figure 1

1.2.2-30, are Seismic Category 1 concrete mechanical draft s truc tu re s . The towers house the equipment required to cool the heated nuclear service cooling water, and the basins provide a cooling water storage supply for the ultimate heat cink.

The plant is arranged so that Unit 1 can be placed in commercial operation before the completion of Unit 2. To minimize the exposure of construction personnel to radiation, to prevent unauthorized construction personnel from entering the Unit 1 protected area, and to ensure that no construction l

3 condition for Unit 2 affects operation of Unit 1, the following measures are taken:

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, Amend. 25 9/86 1.2.2-3 Amend. 35 3/88 i

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INSERT F The Dry Active Waste (DAW) facilities consist of processing and storage buildings. These buildings are located in the South-West portion of the owner controlled area as shown on Figure 1.2.2-1. The DAW processing and storage buildings are metal siding buildings supported on a base slab with tilt-up

, concrete panels and masonary blocks provided for shielding. The roofs are metal decking supported by structural steel. The grade elevation is above that required for natural flood protection. Curbs and ramps are provided, in radioactive areas, to contain water from fire sprinkler actuation. The DAW processing building contains a compactor, sorting tables, waste drying equipment and other support equipment. The DAW storage building has space to store DAW packaged for offsite shipment.

Figures 1.2.2-35 and 1.2.2-36 show the DAW processing and storage building layouts.

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VEGP-FSAR-1 e Power b' lock entry (control' building) .

e Control room (control building).

e Control building support facilitiss (locker rooms,

' showers, health physics office, laundry, first aid station, etc.),

e Radioactive laboratories (control building).

e e Communication room (service building). .

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e Technical support center (control building).

e Hot machine shop (auxiliary building).

e Hot instrument decontamination shop (auxiliary building).

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e Drum storage area (auxiliary building). l e New fuel pit (fuel handling building).

e Spent fuel cask handling areas (auxiliary and fuel handling building).

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e Radwaste transfer building, o Radwaste solidification and' volume reduction area (radwaste building).

l e Alternate radwaste building.

l e Water analysis room (turbine building).

e Nitrogen storage area (outdoors).

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2 VEGP-FSAR-1 paragraph 5.10.8.2 of ANSI N509-1980 will not be performed since two separate interlocks are provided to preclude overpressurization of the ducting, s

Wherever ANSI N510-1975 is referenced in the regulatory guide, conformance is with ANSI N510-1975 or ANSI N510-1980 depending on the date of the applicable purchase order. 22 Conformance may be with ANSI 510-1980 when specifically called out in the corresponding specification.

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1.9.141 REGULATORY GUIDE 1.141, APRIL 1978, CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS 1.9.141.1 Regulatory Guide 1.141 Position The requirements and recommendations for containment' isolation of fluid systems that penetrate the primary containme.nt of light-water-cooled reactors as specified in ANSI N271-1976, Ac fi+ss Wais p <wess4j 7 HVK T/, a- buo */di4 Ory Sy3 Vem i :s u. rly su by 'etf }o /b e. In p/ ate les}/nj grilen'a hor- lAs ex beusb N8P8 44 nt'h Gh lbsls trap /</wy 6 de, s

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30. Store drain 5 U8C-76 System MA 6 2 C org M N .

31. River makeup (Note Y)

S NA 6 2 water piping C AWA C-200 N N

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.. FIGURE 9.3.3-3 (SNErl 11 OF 11)

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4*98 Y 4 i k sm I

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l l

i e

I

~

PW4 !

l VEGP-FSAR-9 1 mechanisms percent of itsto capacity.

allow chiller opera' tion down to approximately 10 9.4.3.3.2.3.7 Radwaste Solidification Building Elevator Machine Room.

outside required, air supply system that provides fresh air,The heated aselevator m ,

to the elevator shaft under positive pressure. l elevator machine room is supplied with outside air from an The intake plenum atmosphere at elat 263 el 263 ft 6 ftin.6 in.; air is exhausted to the This system assists in minimizing bui1 ding. exfiltration from the radwaste solidification ',

9.4.3.3.2.3.8 Health Physics Building. The 100-porcent outside air supply is filtered and conditioned by the air Supply zones. air conditioned to 55'E is delivered to the different controlledEach by azone space is thermostat.

equipped with an electric reheat coil duct is initiated when the spaca relative humidity becomes lower than the preset value of the spece humidistat.

An the air exhaust fan atmosphere collects at el 237 ft all room air and discharges it to 0 in.

9.4.3.3.2.3.9 Alternate Radunate Building.

ridge ventilators are provided for the alternate Continuous radwastemanual building.

the vendor-supplied container vent system to exhaust theA vent l building filtration system.potentially contaminated process air through the a Provisions are included 25 air from the radwaste tunnel area and portions of the to exhauct radwaste transfer building through the auxiliary ha41 ding flitration system prior to completion of the radwasta solidification bugidina.

c37vsstrT 9.4.3.3.3 Safety Evaluation

/

l Since there is no safety design basis ror the radwante solidification ventilation building system , and'radwaste transfer building no safety evaluation is required, l

a a w . m y a s ,,, u , /

i 9.4.3-18 Amend. 25 9/86

m. . , -- '

INSERT G NOTE: Sectica 9.4.3.2.3.10 Addresses ARB Control Roor,and Dress Out Area.

, 9.4.3.2.3.11 - Dry Active Waste Facilities The Dry Active Waste (DAW) Processing Facility is provided with two heating, ventilating and air conditioning (HVAC) systems, and exhaust air system and unit heaters. The HVAC system and exhaust system for the potentially contaminated processing rooms and storage rooms are designed to provide control of airborne contamination. The HVAC unit for the potentially contaminated processing rooms rcturns air from the rooms and individual pieces of equipment (e. g. -

compactor)(HEPA) particulate and recirculates the air through high efficiency filters and cooling coils. The processing rooms are maintained at 70 F while the storage area temperature is not controlled during summer operation.

The exhaust air syctem is designed to maintain potentially contaminated processing rooms at a lower pressure than surrounding areas and the potentially contaminated storage area at a lower pressure than outside. The exhaust air passes through HEPA filters prior to being released.

Testing of this HEPA filter is in accordance with the in place testing criteria of Regulatory Guide 1.140. A radiation monitor (sec. tion 11.5.2) is provided to monitor this effluent path.

Seven unit heaters are provided for the storage areas and mechanical equipment rooms for freeze protection.

Tne HVAC system for the non-contaminated rooms provides outside make-up air while recirculating air through a cooling coil and three duct heaters. The system is designed to maintain these rooms at 75*F.

The DAW storage facility is provided with heat Lnd ventilation. Manually controlled rooftop ventilators

' exhaust air from the building and draw outside air in through several intake louvers. Eight tharmostatically controlled, ceiling mou *ed unit heaters provide space heering for frceze prots.cion during theswinter.

, ,y , ., , - . - , .- , , . , 2 - , - . .

l Peaease.o du a xe. e4

. 'i

, - VEGP-Ir.MR-9 5-TABLE 9.4.3-6 (SHEET 4 OF 4)

{

1 Health Physics Building 'WAC Supply Air Handli'ag Unit Quantity Fan capacity ft1/ min) 1 .,

8 Static pressur(e (in. WG) 2300 Fan (hp) 2.75 5 Coolir# capacity (5tu/h) 2 Heating capacity'(kW) 196,000 Filter efficiency (%) 35 ,

l 80 to 85 !

.J Alternate Air Head 11agRadueste Unit Building Control Room and Drese-out Area Quaataty ?

Faa Capacity (ft0 /nla) 1 1000 Static Pressure (la. NO) 0.70 Faa (MP) -

Cooling Capacity (BTU /N) 0.78 i .

65,000 I Heating Capacity (KW) I 17 Filter Efflolency(*) Low l

i Alternate Radusste condensing Unit Su11 ding Control Room api Dress-Out Area b i

/

f Quantity 1

\ Capacity (BTU /N)

Refrigerest 68.000

., R-23 Fan Noter (W) k F *-- 0.6

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POoPosEO CHAWGes

. VECP-FSAR-9A -

! 9A.I.12 P.,'F IRE AREA 1-RTD-L1-A A. .imcation: _R****** Transfer h l 11dinam- L 2

l E. Figuress. _

sa, ErRL 7A y ,avais y 1, )

e

c. Descriptions j includes fire zones 3005, 301, 304, 303, 30{554] !

m... 1 - .. J. ~ _

1 6detinsgarnfis- _ e ,atte sL 4

D. (pescnytson ~ L M=- -

t

1. Level 1 i Floor

- Unrated coricrete base mat. 3 Nor1.h h-rated barrier separates' area from the 1-AS-L1-0, 1-AS-LD-3.

West h rated barrier separates '

from stairwell No. A. M, i ~

- Unrated exterior area boundary.

h-rated barrier separetes area 24, from 1-RS-LA-A.

South

- Unrated exterior area boundary.

_h X_^

m________ _ _ _ _

East

- Unrated exterior area boundary. -

2.

Elevation 237 ft - 0 in.

North

- h-rated barrier separates are from 1-AB-LD-8, 1-AB-L1-0;

'c

.

r 5euth

- Unrated exterior area boundary.

.s ,,

__m_2 u _ __ a _ _ ______.__ ____

3:S;'5 552 55 East

- Unrated exterior area boundary.

Amend. 15 3/85

- .

Amend. 24 6/85 9A.1.129-1 Amend. 28 11/86

.e a

rwo msen La nc,es -

VE07-FSAR-9A North t

.,_ h-rated barrier separates area from 1-AB-L2-A. -

7

South il'

- Unrated exterior area boundary.

l 2 h ::t:d i ::12:n vy

. *: = ' ! r. *'. .%

:::ts: ::D '

East

- Unrated exterior area boundacy. !

j

West 3

.- 2-h rated barrier separates from stairwell No. A. I E. - Unrated exterior area boundary.

Area Access a

1. Level 1 North -

j- f- -

West -

Class A door from 1-AS-L1-0.

East c3 Class A door from stairwell No. 44

~ 7nrated .

g 2. rom outside.

- Elevation 237 ft - 0 in. (

East -

1$

3. Level 2 Unrated door from stairwell No. C.124 g

West g F. - Class A door free stairvell No. A. I Scaled Penetrations a Seals meet or exceed fire barrier ratings.

G. Fire Dampers

{

f$ j b Fire dampers meet or exceed fire barrier ratings .

H. SIhfeShute;.g. Components t l i e

I I.

Sa'fety-Related Equipment No major equipment.

J.

Nonsafety-Related Equipment Two phase separator tanks and pumps Amend. 15 3285 Amend. 24 6/86 9A.1.129-2 Amend. 28 11/86 l

l l

~~~ ..

Peocasso CH w-m VEGF-FSAR-9A

" f, dee==* en11actina tanh*_

pumps

, K.

, sudl & 6MPM .

1.' Zone No. 3005, Fixed combustible quantities i

Cable insulatio hypalon value) n (equivalent Charcoal 0 lb j

- Cellulosic Oil / grease materials 0 lb 0 lb Plastics 0 lb Rubber goods -

0 lb #) t O lb

+

Heat release

- (

- Fixed combustibles Transient combustiblen 0 Stu '

400,000 ste,

' Combustible loading

1,754 Btu / a. M Fire severity (wood equivalent)

2. 2ene No. 301 1 min Fixed combustible quantities Cable insulation (equivalent hypelon.value)

Charcoal '

0 lb

- Cellulosic Oil / grease materials 0 lb 1'

0. Ib Plastics 0 lb Rubber goods 0 1h

0 lb Heat release i -

. Fixed combustibles

. ..i, - ..

O Btu

'fransient combustibles 400,000 Btu Combustible loading

.

633 stu/ft8 Fire severity (wood equivalent) Negligible

9A.1.129 3 Amend. 15 3/45 Amand. 24 6/84 l

P

, ,---- - - - - - - --,--,-.,-- -,,-- , ,, ,, ,,---- ,-n,--,--e

- %ennan Ca n su.es vrar-rsaa-sa a 9' - Cellulosic oil / grease materials

~" 0 lb

'l Plastics 0 lb Rubber goods ' 0 lb

O 1h Heat, release Fixed combustibles ,

Transient combustibles 5,003,260 Stu i

800,000 Btu Combustible loading

+ 24,281 Stu/ft8 re severity (wood equivalent)

L. Eva us 18 min on of safe Stnitdown capability J

1. -

ForS.a or fire in this area, use safe shutdownanA Tr i 2.

Special operational and design consideration s None. .

d

3. .

Spurious actuation considerations: .

Non. .e.

M.

15 24 Fire D;etection .

Early warning following zones: fire detectors are installed within th ,

e Zone 3003 '

3 Zone 301

(,, same so. ase ,

s

. rises esen'aatte essoasues Cable Ea'r = a(ega. 1lvalems asset

- Celteneese os vessees notettait. 7890 14 Plaettes soo1m I hebber gases Seelh

, . 440LD ames rStones e

M hMehlM l

, . Tremotest eseestah&as , ,,, .. .-

kosaheettuatoediae

- ' ris. .meser tvees ses,etect @'ft*

19 ass Amend. 15 3/85 9A.1.129-5 Amend. 24 8/84

' Amead. 23 11/84

-..__ ,._9 __ , _

Pn e en- = Gu ue as.

WGP-F5AR-9A fjZone302

.t . Zone 303 - f' l

W N. Tire suppression i

1. Automatic t

Zone 3008 - No sone coverage.

Zone 301 - No sone coverage, j

Zone 302 - No sone coverage. -

Zone 303 - No sone coverage.

_ _ 3an. 1oL -

2.

i ' 3*44 ~Sto ; Q as causea w _

WarhitihmTMM aema covannsa 5M "MA, - -

= :2:

Hose stations (with to portable extinguishers) ear :5 24 conveniently located each area. Any location stream.

can be reached with at least one effective wa i

2

\ e 1

1.

. '; o

\ .

Amend. 15 3/85 9A.1.129-6 Amend. 24 6/06 Amend. 28 11/86

~ __ - - .__ .- - ^

\

) . Peoeosab CH A tmes l i

VBGP-FSAR-9A i i

. I i

0.

(

Radioactiva

.* Materials .

Raittoective liquids.

F. lation -

' .eeks can be removed using the neraa.

l ventilation

, aystem in a omeo-through only mo l

' areas isolated by fire dampers, de of operation. yor i portable fans using fleaible tubes to direct the smokesmoke{ - .

to an area capable of being ventilated or directly o t

~

outside. l i

Q. Drainage Secause there safety-related are ne safe components in this shutdown area ,/or and -

! consideration has been gives to fleeding.ne specisi R. Einergency Lidting 8-h-rated ogress battery fixture (s) provide safe ingress /

of personnel. i S.

Deviati,ons and Just11.esticas

1. ,

NN Unrated asterior fire area wMan:

See Appendia 93, section C.S.a(1).

V N f.a4;..4.vedrywaste t

i Let>1evel intermediate-level radiometive waste in solidtfica*4em g ,, --

material, which in tura is in motst Solid low-level radioastive waste.

^

' Amend. 15 3/85 gn.1.123-7 Amand. 24 6/84 Amend. 28 11/88 g .n

. Peopnsen (_.a Aus.es vamp 'Fsaa-sA 9A. 1. Y

, \

DELETEb ,

Y.co.ation: A2t.rn.t..ned.ast. !

4141 ,

4. Figures:

9A-43, 9A-43, and 9A-44 C. scription:

Includes fire mone 330 t

, ! Al 230 raate t.S in.) radwante building (one level ructure, el D. i Descri tion of Soundaries Floe

- Unrated concrete be mat. '

Ceili

- Unrated exterior boundary.

North 3-h-rated barrie separates area free 1-RTS-L1-A.

~

West -

ated exteri r area boundary e

south - Unr ted este or area boundary. n.

East - Unrat sa E.

rior area boundary.

Area Access

O East - Unrated outside.

Wsat - Unrated rf outside.

- Unrat roll-up l

F.

r from outside.

Sealed Penetrat on Seals meet or ceed fire barri ratings.

O. Fire Damper Despers '

. t or asceed fire barrier ratings.

H. Safe Sh' t c Componects None.

I. Safe Related Equipment No .

I f

_ Amend. 25 9/86 9A.1.131-1 Amend. 23 11/86

.. p .

~

% paeen (nawAse

~

VROP-FsAR-9A Massafety-Related Equipment i

Temporary radwaste process equipment.

K.

stible Loading

1. Zone No. 330 t 3 I

j";

Fixed combustible quantities .-

cable insulat:1on (equival hypelon value)

Charcoal 0 lb l

- ellulosic

,1/ grease natorials 0 lb 5570.lb l a

- P; stics 1600 lb r goode 0 lb 0 lb Heat to ase '

Fixed stib e . . 1' Transi tc e

tibles 76,560,000Staa'j6 77,360,000 at:4 i ,.

Catbustible ng 55,164 Rtu/ft*

l.28

' Fire severity wood equivalent) 41 miis L.

Eiraluation of Saf Shut :. Capability

1. For a fire this a or B .

e, use safe shutdown Train A

2. Special rational and. sign consideration None.

3. S ous actuation consider ions gW -

M.. ptectio. :n ly warning G re detectors are inst c11owing nonr!.: led within the

Zans 330 9

t

. a' t

9A.1.131-2 Amend. 28 11/86

~

Peopme t'MAMER !

VEGP-FSAR-9A

. 'g, Fire suppression

. '1. Automaelc Zonecoverage.

zone 330 proaction sprinkler system - P ial e

2. Marical e

a rtable area.eatinguichers are convenient located in

o. Radioac ve Materials Radios inve liquids

, d Radiacti drywaste 1

Low-level solidificat.. termediate-level

material, adioactive vaste in

/ in turn is in meta) !

Solid low-leve radtonct waste. )

P. Ventildtion '

g, 13 Smoke can be removed tubes to direct the portable fans using flexible outside.

Q. Drainage Because there are safe safety-related e nents i tdown ara /or consideration been given to flooding.this fire arma, no spe R. Emergency Li ir.g 8-h-rated tery fixture ingress / se of peruonne(l.) pro de safe S. Deviatto and Justifications o Var exterior fire area bounda t

5 Appendix 95, section C.5.t.(1).

e' ,

9A.1,131o2 Amend. 28 11/86

PReph CWAMAES l 1

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t Aanend. 15 3/85 Asnand* 24 6/86 may 3 FIRE AREA 5 RADNASTE TRANstr.R BUILDING LEVII, 1 FIDom pr.Au ut, 220e 0" FIGURE 9A-42 1

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t Amend. 15 3/85 Amand. 24 6/84 new.t FIRE AREA 5 RADivh5TE TRAN5FM

' BUILDING PARTIAL LEVEL 1 l FLOOR PL1_M EL. 237'-O

FIGURE 9A-43

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Amand. 15 3/85 Amend. 25 9/84 hM kTano h - - - - -

new.a FIRE'ARe 8 RADMASTE -

TIUuSSFER BLDG. LEVIL II FLOOR PIJul EL. 247'-0" FIGURE 9A-44 L

4

VEGP-FSAR-ll

{

H. Provide temporary onsite storage of packaged wastes in the event of delay or disruption of offsite shipping schedules. ,

{

I. Package radioactive solid wastes for offsite shipment

' and burial in accordance with applicable Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regulations, including 49 Code of Federal Regulations (CFR) 170-178 and 10 CFR 71.

The solid waste management system is designed and constructed in accordance with Regulatory Guide 1.143, as described in -

saction 1.9, to meet the requirements of General Design Criterion (GDC) 60 of 10 CFR 50, Appendix A. The seismic design classification of the radwaste transfer building, radwaste tunnel, and radwaste solidification building, which collectively house the volume reduction and solidification system, and the seismic design and classification for the system components and piping are provided in section 3.2.

Provisions are made in the radwaste solidification building to utilize a mobile radwaste solidification system in the unlikely event that the inplant system becomes unavailable for a prolonged period of time. In addition, an alternate radwaste building is provided to allow use of portable radwaste systems 25 (demineralizers, dowatering/ drying, solidification) supplied by contractors for handling solid wastes from plant operations during fav%'kesallm plant conditions jmwded (section is pneese n.ed s 11.W hee, 94 42 Ay//,vrtaasNee), wad M (s.4). r /

esHoe j

The solid waste management system design parameters are based l

on the radionuclide concentrations an'd volumes consistent with operating experience for similar reactor designs and with the l source terms of section 11.1.

The solid waste management system airborne process effluents are released through the radvaste building vent and are discussed as part of the 10 CFR 50, Appandix I analysis presented in subsection 11.3.3. '

~

The solid waste management system is designed to collect, solidify, package, and store radioactive wastes.so as to maintain radiation exposure to plant operation or maintenance

, personnel as low as is reasonably achievable (ALARA) in accordance with CDC 60 of 10 CFR 50, Appendix A, and Regulatory Guide 8.8 in order to maintain personnel exposures below 10 CFR 20 requirements. Design features incorporated to maintain ALARA criteria include (but are not limited to) remota r.ystem operation, remotely actuated flushing, and shielding of components containing radioactive materials. Additionally, access to the process equipment and solid waste storage areas is controlled to minimize personnel exposure by suitable barriers such as locked doors or gates or control cards. (See Amend. 5 4/84 11.4.1-2 Amend. 25 9/86

, - , _ ~ _ .

VEGP-FSAR-11 the drum enclosure for handling waste spillage. Fire protection provisions for the flammable polymer are discussed in subsection 9'.5.1.

11.4.2.3.10 Packaging, Storage, and Shipment oe opedry Hvaf,kr*kkyj

' Solidified wastes, spent filter cartridges, and soli compactible wastes are packaged in 55-gal drums accordance with 49 CFR 173.395(a)(1) and shipped in shielded casks, as l19 required, to meet 49 CFR 173 dose limitations of 200 mrem /h at the external surface of the transporting vehicle and 10 mrem /h at 6 ft from the external surface of the transporting vehicle.

The 55-gal drums used in the volume reduction and solidification system meet the requirements of Specification 17H, as specified by 49 CFR 178.118, or of Specification 17C, as specified by 49 CFR 178.115. The 17H drum is used for processes requiring open-top drums, and the 17C drum is used for processes requiring a closed top drum with a screw cap.

Packaged solid radwaste is stored in the intermediate level or low level solid radwaste storage areas as shown in figure 1.2.2-33. Unused, uncontaminated shipping containers are stored in allocated storage areas.

The radwaste storage facility has limited access areas allocated for intermediate level and low level solid radwaste.

These areas are shielded and remotely maintained to limit D?b o $W a 5,,Y5Y$s el 4 mA on //, V:.r.g' The shielded storage area for intermediate Aavoi .vlid sed #aste contains 834 ft" of usable floor area.' The shielded area for low level solid radwaste contains 992 ft storage 8

of usable floor area. In addition, the storage areas are designed with the capability of stacking the filled drums (up to seven high) for additional storage capacity. This onsite storage capacity exceeds the expected quantity of drummed waste for 1 year of plant operation as stated in table 11.4.2-4. Shipment of solidified waste is expected to occur well before 1 -year elapses.

Although compacted and solidified waster are expected to be

' stored onsite prior to shipment, generally no credit is taken for radioactive decay realized by such storage when filling drums for shipping in accordance with 49 CFR 173 dose limitations; that is, once filled, drums can normally be shipped immediately, with the proper shielding, without exceeding Department of Transportation (DOT) radiation limits.

f 49 CFR 173 dose limitations cannot be met with the available 11.4.2-19 Amend. 19 9/85

penswath enuAE VECP-FSAR-11 i

1 11.4.2.4.2 Portable Radwaste System I VECP will utilize vendor-supp1.ied portable radwaste equipment to provide for disposal of spent resins, radioactive cartridge filters, evaporator concentrates, backfluchable filter crud, and chemical wastes via dewatering or solidification. In addition, a portable domineralizer system is available as an alternate means of processing the contents of the waste holoup tank chemical drain tank, floor drain tank, and boron recycle noldup tank. These systems are housed in the alternate radwaste building (ARB) which is located on the south side of the radwaste transfer building as shown in figure 1.2.2-33.

Isolation valves are provided to allow processing of waste streams either with existing systems or at the ARB. The valves are manually operated to achieve the desired configuration.

Delivery of waste streams to the ARB is controlled from local panels near the waste atream source. Flanged connections are provided at the ARB to interface with the vendor-supplied systems. Major components for portable radwaste systems typic allu-_4=d uAM - ===_Ainers p rocess akids. and_ control _

anmin.f A *a pe ra.+ e ARS conTro n ceom a,n A ace gent o.ce n.

'ack'pfev'Ae1 4e (m ed i 4+A e sg 4em a p a ra.No ref ,

RadioactbTe cindensate %1TsTiing d3iiineralizer resins, backflushable filter crud, and spent resins from the liquid waste processing system and the steam generator blowdown system will be dowatered. The dewetering system supplied by vendor allows the water to be removed from the spent resins in the shipping containers. A vendor-supplied container vent is provided for the shipping containers thereby minimizing leakage into the building. A vent line to a monitored HVAC exhaust duct in the auxiliary building is provided to interface with the vendor system. In addition, domineralizer resins from the portable domineralizers (ab discussed in section 11.2) can be sluiced to the container fill. skid for dewatsting and disposal.

An NRC approved process control program (PCP) will be required of the vendor and appropriately referenced in the VEGP PCP prior to any actual operation. If the burial site does not accept dewatered resins or the waste form criteria cannot be met, VECP will have the ability to solidify resins utilizing a portable solidification system. Cartridge filters will be loaded into liners for shipment offsite.

CktMR- -$ __N, 5_ ._ U.I.I.[.'".

!. b. 5 EY.. E2..I. .b...'.."NI5...

s y . IY. N.. ". .m 5..."Y,".N.. ..

p::tcr h:: On int:gr:1 chroud-which-dkrect- any airborne duct: r;;ted by th; ;; p;;ti;r ;;;eet4;r th : ugh er enhauet fen-74nd filte -and then te the hRO ventiletic. rist.&.

11.4.2-24a Amend. 25 9/86 i

l 1

VEGP-FSAR-ll l

Solidification /dewatered liners will.normally be shipped after filling and proper cure time, provided the proper shielding is available, without exceeding DOT radiation limits. If 49 CFR 173 dose limitations cannot be met with the available shielding, the liners are stored and allowed to decay until the appropriate shielding is available. 25 Onsite storage for decay of i short-lived radionuclides is accomplished both prior to solidification in holdup tanks and in appropriate onsite storage areas.

y= 2 Add ll Yo 2.a 5 '

wsser A l

l ll.4.2-24b Amend. 25 9/86

INSERT A Page 1 of -A

~

1 11.4.2.5 Dry Active Waste Facilities Two buildings have been designed for handling dry active

, wastes from plant operations:

A. The Dry Active Waste Processing Building is used to sort and compact dry active waste.

B. The Dry Active Waste Storage Building is used to store compacted dry active waste packaged for shipment offsite.

11.4.2.5.1 Dry Active Waste Processing Building Dry Active Waste (DAW) is transported to the processing facility in containers which will prevent any leakage of radioactive materia) during conditions incident to normali transportation. The radioactive material is packaged such that contamination on the outer container surface is below administrative limits. The transport path remains within the owner controlled area.

The DAW Processing Building has separate areas for incoming radwaste containers, sorting and compaction of radioactive waste, handling of non-radioactive dry waste, and storage of empty containers. The DAW is sorted to separate usable i material, radioactive and non-radioactive waste.

l Radioactive waste is compacted into packaging that will comply with the criteria of 10CFR Part 71 to minimize the l need for repackaging for shipment.

A dry waste compactor is provided. The compactor has an integral shroud which directs any airborne dusts created by the compaction operation through an exhaust fan and filter and then to the building ventilation system.

The building has lockable doors and is enclosed by a fence with. lockable sates. The purpose of this fence is to prevent unauthorized personnel from entering a radioactive area. Security patrole verify building security.

s I

i .

1

\

l Page 2 of 3 The building is provided with automatic wet pipe sprinkler l systems designed for an Ordinary Group II Hazard.

Ionization and photoelectric smoke detectors are provided.

Smoke detectors actuation or sprinkler head water flow initiates local audible / visual alarms external to the building. A fire hose station with portable extinguisher is provided.

The waste container materials used do not support combustion.

11.4.2.5.1 Dry Active Waste Storage Building ,

DAW is transported to the storage facility in packaging that will comply with the criteria of 10CFR Part 71. The waste is stored in the interior of the building. Lockable doors and a fence with lockable gates are provided.

The building is provided with automatic wet pipe sprinkler system and smoke detectors. Fire alarms external to the '

building are provided. The waste container materials used do not support combustion.

M e

\

VEGP-FSAR-ll I

. l 11.5.2 SYSTEM DESCRIPTION l

11.5.2.1 Digital Radiation Monitoring System The process and effluent radiation monitoring system (PERMS) is based on a distributed digital microprocessor approach, where each radiation monitor is self-contained and consists of a detector and a data processing module (DFM) that contains the microprocessor.

PERMS channel. Each The DPM is the basic control center for each complete channel consists of a monitor d with power supply and preamplifier; a local dedicated data processing module containing a digital buffer and microprocessor with alarm outputs; and access to readout modules (cathode ray tube (CRT) and printer).

The PERMS collects and displays all the information available from on the field-mounted detectors on a CRT and hardcopy printer j demand. This is accomplished by either the communications ?

console or the the control room. safety-related display console (SRDC) located in-The communications console receives data from the DPMs (both standard and safety-related) and interfaces with a minicomputer and the technical support center (figure 11.5.2-1). The SRDC displays data received from the safety-related channels which are composed of safety-related Class 1E components (figure 11.5.2-2). The safety-related DPMs also

' interface with the communicaticns console with one-way data transmission.

{ 11.5.2-3._ _

--Thu communications console is shown in figure i

(f W 5 6t,7 & '

11.5.2.2 Monitor Description The radiation monitors fall into five different functional classifications:

A. Process monitors, which determine concentrations of radioactive material in plant fluid systems.

B. Effluent monitors, which measure radioactivity discharged to the environs.

C. Airborne monitors, which provide operator information on airborne concentrations of radioactive gases and particulate radioactivity at various points in the ventilation system ducts. (See figure 11.5.2-4.)

D. Area monitors, which provide operator information on external gamma radiation levels at fixed points throughout the plant.

11.5.2-1 l

t

4 I

Page 1 of 1 INSERT B - -

11.5.2.1.1 Dry Active Waste Processing Building The Dry Active Waste (DAW) Processing Building radiation monitor consists of a lead-shielded particulate sampler and detector, a count rate meter, recorder and sample flow e indicator. The monitor has a local visual and audible high radAuilon alarm. A remote visual and audible high radiation alarm is also provided in the non-radioactive storage area.

The particulate sampler will be changed and analyzed weekly in accordance with plant procedures. The offsite dose calculation manual (ODCM) includes the DAW processing building as a potential effluent release path and incorporates the sample analysis results in the offsite dose calculation.

k

_ _ _ _ . _ _ _ _ _ _ . _ _ _ _ . _ . . . _ _ m

VEGP-FSAR-ll E.

Post-accident (or high range) monitors, designed to assess and follow potential pathways for release of radioactive materials during accident conditions.

Table 11.5.2-1 gives the design parameters for the PERMS .

4 Table 11.5.2-2 lists the detectors used in the PERMS. -

Table 11.5.2-3 lists the conditions of service for PERMS .

. liquid and gaseous release pathways, Figures 11.5.2-5 and 11 design parameters for flowrate monitoring.and table Figure11.5.2-5 12.3.1-3gives the 5 shows the detector locations.

11.5.2.3 Moni tor Functions jg-7 The PERMS con shared), ts of 23 area monitors 8 per unit and 7 process and effluent moni (27 for Unit 1, 28 for Unit 2, and rs (subsection 11.5.2) monitors (subsection 11.5.5) (10 per unit), shared), 20 post-accident passive activity collectors (5 per unit) planned forincluding 10 3 installation at the VEGP site. ]5 areas ofare monitors theidentified site thatby are an common "A"

to both unite.Some These monitors i

number (i.e., ARE

). in front *of the monitor's tag The following is a description of each monitor:

A.

Airborne Process and Effluent Monitors

1. RE-12442A - Plan' Monitor (Low Range)t Vent Efflunat Air Particulate The purpose of this monitor is to continuously monitor air particulate activity as it is discharged to the environment through the main plant vent and provide data necessary to ensure that particulate vent are below specified activity releaseslimits. from the plant t The monitor also se'rves as a backup to the containment vent particulate monitor RE-2565A.

i

. Since the main plant vent discharges directly to i the atmosphere, the data from this monitor are l

most releases representative to the plant environs. of particulate activity activity exceed a specifAed level,Should the '

t a high radiation level alarm will be annunciated to indicate has occurred. that an increase in particulate release i

The specific source of release within the plant may be determined through analysis of the monitors upstream of the vent /

monitor and/or with portable monitoring devices.

11.5.2-2 Amend. 5 4/04 l

~ ~ - ' ~ ~ ~ ~ ' ' ' '

VEGP-FSAR-ll T,he vent, activity is filt6 red and routed to the plant vent monitorswhere RE-12442A, it is again monitored by the plant discLarge to the atmosphere.

B, and C prior to In the event of a I fual handling accident inside the fuel handling building, ARE-2532 and ARE-2533 are capable of l 8

detecting the high activity in order to switch the 1 fuel handling building ventilation system from the l normal operating mode to the accident mode, which i includes safety-related filtration units. (See i subsection 9.4.2.)

23. J ARE-50003 Process Radiogas - Technical Support Center Air _ Intake Monitor The purpose of this monitor is to continuously monitor the technical support center supply air for gaseous activity that could be present in the atmosphere following a contamination accident.

A high alarm signal will alert personnel in the '

technical diological support center of a deteriorated condition.

B. iqu Process and Effluent Monitors 1.

ARE-OOl6 - Boron Recycle Liquid Process Monitor .

The purpose of this monitor is to continuously monitor the boric acid, evaporator distillate for high activity, which would be indicative of an evaporator malfunction.

A high alarm signal will initiate diversion of distillate flow from the reactor makeup water storage tank to a recycle holdup tank via the evaporator feed domineralizer.

Remote readout is provided at the boron recycle system panel. l 2.-

RE-0017A and B - Component Cooling Water Process Monitor The purpose of this monitor is to continuously monitor the component cooling loop for activity indicative cooling component of a leak of radioactive water into the system.

11.5.2-10 Amend. 35 3/88

_____ _ ___ ____._______ ____ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ . _ _ ~ . _ _ _ _ . _ _ _ _ _ _

INSERT C Page 1 og }

24. ARE-13256 - Dry Active Waste Processing Building Effluent l Particulate Monitor I The purpose of this monitor is to continuously monitor air particulate activity as it is discharged through the DAW s

Processing Building Ventilation exhaust and provide data to ensure that activity releases from the building are below specified limits.

This monitor has visual and aucible alarms locally and remotely in the non-radioactive storage area. The remote alarm is located adjacent to the ventilation system controls. Upon alarm the ventilation system exhaust can be manually isolated.

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VEGP-FSAR-11 l

These components and waste include the recycle evaporators evaporators.

1 e A high alarm signal provides operator warning so that action may be taken to avoid further radioactive contamination of the auxiliary steam condensate.

Remote readout is provided at evaporator steam supply system panel. l

9. RE-1950 - Auxiliary Component Cooling Water Process Monitor The purpose of this monitor is to continuously monitor the auxiliary component cooling loop for-activity indicative of a leak of contaminated -

water into the auxiliary component cooling system.

10.

RE-17646 - Control Building Sump Effluent Monitor The purpose of this monitor is to monitor the control building sump discharge and provide data necessary to ensure thht the liquid discharges from the control building are below specified limits.

A high alarm signal initiates automatic isolation of the discharge line to prevent further activity releases.

11.

RE-48000 - Chemical and Volume Control System Letdown Monitor The purpose of this monitor is to monitor the chemical and volume control system letdown liquid process and provide indication of abnormal activity levels in the reactor coolant system. .

11.5.2.4 Alarm Setpoints Each of the PERMS airborne and liquid monitors (excluding passive cartridge monitors RE-25628, 12444A and B) has two alarm setpoints,RE-12839A and B, and RE-i.e., intermediate high.4 When setpoint, the radiation level being monitored reaches the and antermediate personnel of the monitor reading.a visualIfindication alerta plant reached, an alarm will be annunciated. the high setpoint is also triggers the control function for those monitors soThe high alarm setpoint equipped: gas monitors RE-2565A, B, and C, RE-12839C, RE-12116, RE-12117, ARE-13133A, B, and C, ARE-OO14, ARE-2532A g gg*)32[fr ksf O rf f

4 b!f Al4%

11.5.2-13 Amend. 35 3/88

e TABLE 11.5.2-1 (SIIEET 4 OF 7) s.ue-ber

' of Proc-Me- stDn!- Duct

sarety ctani- selseic ess Size /Page tors seonitor Classiri- col Guastri- per seoving flog Automatic Dienster sanni tor Twee g;ation (rte / Contros sea te rie s , Power Gada cation tini t filter han ment function schedule Susolv a

toaste cas Decay Iank fat-0039A and a Prucess, sesas esA (C rer Unit 2 onsy) insene-seo 2 Sue / soone 136 in, soon-cla ss (unit s200(.

t) x 36 in. It gunit :) Assn 3 500/

(unit AS2 7, 1:00/ 16 gauge 23 a00 <

fue: Mendling Suilding lunit 25 p E rr s urgt O AME-2532A and a Errsuent SC-3/IE IIA m

AAE-2533A and a Yes Common 3 insane 32,700 Yes:

suitches buiseing 36 isa. x 36 in.

Cseas 31 l M tn to acci-Assa AS27 N

dont mode is gauge or opere- 8 tion in- M V

cauding

. sarety-reseted restration mai t s lechnical Support 2* > Center SU Amt-50003 Process, S8 seses esA seu Gammon DU insine 1200 sect.e 20 in. x IJun-C s a s s OO Its in. If dieses

AslM backed AS2K L.s _ 18 gauge UI tah ZFSE"rp

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?ABLE 11.5.2-1 (SHEET 4 op 7) ,

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m i.or .t as- 5* 8-se ,.

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TABLE 11.5.2-2 (SIIEET 2 OF 3)

Radiation Detector lone Detectable Menetor Lssatio.D Iv80 mange 1fWI/hl _ Ms.ior. Isotoseg 3 i

Contro8 Hooo Air Intake . tuC e /cm J _

Af-12886, R[-52337 Cosot rol room thin walled <0.2$ Me-133, Xe-135. kr-aS. 2-133, C-M tusnes t-133, Co-SS, 00-60 1.01-6 to I.ot-1 Weste Cas Processing System RE-0013 Aum bldg C-M tubes 2.5-15 xe-833, xe-335. Er-sS 3.Of-I to 3.0E+4 Vola.ee Reduction Rooms Exhauss AML-l'333A (particulate l Radweste Seta <2. S solidife- scint488ation 6-138, 4-133, Cs-134, Cs=331, 1.01-15 to 3.0[-6 cation badg Co-SS Co-60 ARL-833338 isodine) Radwesto Comea < 2. S 6-131, 8-133, 4-13S solider 8- scents 8fation l.ot-il to I.0E-6 4 cation b8dg M Amt-33333C tradiogasi Madweste meta < 2. $ O susfeife-cation tidg scint e 8 Ba t losa xt-II), xe-83S, kr-aS 5.01-a to 1.of-3 y st. C.s ,,.coss. g System Effluent Am[-col 4 Aun bl#<3 C-M tube

. g 0.2S-2.S xe-13 3, xe- 9 3$, k r-SS 1.O(-l to I.OE*4 g Weste Gas Decay tank g AE-0039A, S, and C Aum ktdg ~H

then watsed 0.2$-2.$ Me-t33 Me-935..kr-45 C-M Eube 2.5-55 1.01-6 to 3.ut-1 2.5-15 fuel Handling Su,8 ding Effguent "t* AML-2532A and 8 3 s aaer s Ihnee w Iestd e s . .", .* . S xe-133, Xe-135, Mr-SS d

(3 AR'. 2S33A arid 5 feasse8 8 e seg G-M Ladees 1.O(-6 to I.Of-l 3 DIdg g O=

technecas support Coaster Air antake g AAl-50Q3 lechseica l thin walled g (0.2$ Me-133, Xe-135, kr-4) support C-M tute 3.0[-6 to I.ul-I conter LJ N

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- ( */ l TABLE 11.5.2-2 (SHEET 2 OF 3)

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TABLE 11.5.2-4 (SH'EET 1 0F 2)

ALARM SETPOINTS FOR PROCESS AND EFFLUENT RADIATION MONITORS I

8 Initial Satpoints (uci/cm') -

Cas Monitors Intermediate High .

RE-12442A 2E-11 3E-11 RE-12442B 25-11 4.8E-11 RE-12442C 1E-6 1.5E-6 RE-2565A 2E-11 4E-11 RE-2565B 1.5E-10 1.5E-9 RE-2565C 1E-6 8E-6 RE-2562A 1.5E-11 as 2E-11 an RE-2562C 7.5E-7 a* IE-6sa> v RE-0024A 2E-10 1E-9 RE-0024B }.

lb6 1.5E-6 '

ARE-0026A 2F-11 8.8E-10 *-

ARE-0026B 3.7E-11 7.9E-10 ARE-0026C ,

4E-8 8.8E-7 RE-2562B -

NA, passive monitor RE-12116, RE-12117 2E-6 3E-6 RE-0013 3E+1 1E+3 ARE-13133A 1E-10 -

IE-9 ARE-13133B 9E.11 9E-10 ARE-13133C 1E-7 1E-6 ARE-0014 2E-1 , 3E-1 RE-0039A, B, and C 2E-6 3E-6 ARE-2532A and B 2E-6 b' 3E-6ebs ARE-2533A and B 2E-6'h' 3E-6tb>

ARE-50003 2E-6 3E-6 ggs.-Isart.1 -

'M l

Eshbbl>ed based o., byHe 0 $$s,'le Oo.se Ghulakone/ Mone/

Amend. 35 3/88

t

's ,

VEGP-FSAR-11 TABLE 11. 5.2-5 (SHEET 2 OF 2 )

Equipme.nt Control Pathway _. Number _ Range Room Local a _ Indication Indication Fuel handling AFE-2532 0-27,000 building Yes Yes AFE-2533 sf8/ min exhaustib>

Waste gas AFE-0014 0.2-2.0 Yes Yes '

processing' effluent' sf*/ min Oy AN64. Aff")32S6 0~S0'O & fes Wash rwestsy' .s 9 '/mo'n f

b,L1 efLJ -

a.

These pathways are not equipped with a release flowrate measuring device due to the fact that radioactivity exceeding j preset limits is not sent to the environs but instead to the respective waste processing systems.

b.

vent These pathways monitor. are also monitored downstream by the plant 0357V ' Amend. 5 4/84 feed Amend. 35 3/88 I

\

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1

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i n ges "i".% e4 yogf g aat stat "1.?* *LANT vm la 4 $4

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13.000 *"'

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OTH.'R 900Act8-Usea m 4.=

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,,,,3,,

800 at seasc OTHER SOURCES

ALL PLOwAAf tg IN PT /h68M 3 c, -

O moNotoal#4 LOCAt'0*'s Ainend. 35 3/88 voogte tts PERMS NORMAL CASC'.lS EFFLUENT GeorgiaIbwtr i=4,ciar,atNamatimeo iA=.U ,2 rtaNT RELEASE P4tilWAY

=

FICune 11.5. 2-ti

TABLE 11.5.3-1 (SalEET 3 OF 3)

Monitor ftund Samose scentification .

L9Catton lEne Purootg RE-12444A vent i sa t ion RE-124448 At monitor Passive AE-12444C (gaseous air errsuent pa rticula te Provide qisantitative activety release data. Ca s ibra tion release pathway) ca rtrsdge Passive iodine of continuous monitors.

ca rtridge 25 Radiogas Vapor sample -

AAE-50003 Technical Technicas Radiogas and

. support contar support conter Iodine Determine isotopic activity

. \ air intalie air intake in technica s suppert center A following accident.

duct ARE-13256

PTW fr** ton 7 Af >.re lea. 5,f,Qfe (rua-> <deg,sc ,f,orsa(e p a.),k / u f* * "7) ~ B- */A *=7 EHLauf ,j,,,, ,,7 y Gt,u fou ,,Ca..A:,asa.s ave. /,,,, @

Q y

t m

. 3*

N .

s W

H I

/

3 Q

a. Ittese monitors require saapilng in acCordertCe Witf3 Regulatory Culds 1.21 25 z.

On

/

VEGP-FSAR-12 12.2.1.4 Stored Radioactivity The principal block buildingssources are of activity not enclosed by the power i e The refueling water storage tank.

e The reactor makeup water storage tank. e

(~ e The condensate storage tanks.

e 7)r e. Eq se Nve wasle Sforefe fauA'N*J ~*

The content of these tanks is processed by the spent fuel pool ll purification system, liquid waste processing system, or boron recycle system until the activity in the fluids is sufficiently low to allow the shielding afforded by the concrete tank walls to result in surface dose rate less than 0.25 mR/h.

Radionuclide inventories of the refueling water storage tank, reactor makeup water storage tank, and condensate storage tanks are presented in tables 12.2.1-50 through 12.2.1-52. No other radioactive fluids are stored outside the power block and radwaste buildings.

Spent fuel is stored in the spent fuel pool until it is placed in.the spent fuel shipping :ask for transport offsite. Storage space is allocated in the radwaste building for storage of spent filter bottoms, andcartridges, solidified spent resins, evaporator chemical wastes.

plant structures are shielded soRadioactive that there wastes is Zonestored inside I access outside the structures. If it becomes necessary to temporarily store radioactive wastes outside plant structures, radiation protection measures are to be taken by the radiation protection staff to ensure compliance with 10 CFR 20 and to be consistent with the recommendations of Nuclear Regulatory Commission Regulatory qui _de_8.8. ,

i 12.2.1.5 Field Run Pipe Routing The procedures for routing of radioactive piping are discussed in paragraph 12.3.1.1.2.

I l

12.2.1-11

. - _- x t

1

. 1 INSERT H The Dry Active Waste (DAW) facili' ties process and store DAW.

Radiation shielding is provided such that the dose rates at outside areas are maintained at less than 0.25 mr/hr. Radiation levels outside the fenced area are maintained at less than 0.06 mr/hr. This1.0 is less than willmr/

assure year.that the dose rate at the site boundary Interior cotcrete shielding is a

provided to limit exposure to personnci during waste processing. The ALARA methodology of Regulatory Guide 8.8 and 8.10 has been used in the design of this facility.

a 6-02129-37

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- VEGP-FSAR-12

-~~ -

12.3.4 AREN RADIATION AND A!RBORNE RADI0 ACT INSTRUMENTATION '

The radiation stonitoring system consists of the following :

, A.

Area radiation monitoring system (ARMS).

, 8.

Process (PERMS). and effluent radiation monitoring system C. Sampling system.

D.

Post-accident monitoring systems (PAMS) radiation monitors. J The PERMS, sampling systems, described in section 11.5. and PAMS radiation monitors art 12.3.4.1 Area Radiation Monitorine The ARMS is provided to supplement the personnel and area.q-described in section 12.5 and to ensure complian personnel 10 CFR 50, radiation protection guidelines of 10 CFR 20 8.12. 10 CFR 70, and Regulatory Guides 1.97, 8.2, 8.8 ,

, and The design ofnormal all postulated the fuel andpool racksconditions.

accident precludes criticality und er Therefore, criticality Guide 8.12,monitors, ars not needed. as stated in 10 CFR 70.24 and Regulatory 4

NSSST 12.3.4.1.1 Dssign Objectives The design objectives of the ARMS durir.g normal operatt ant g pl conditions and anticipated'

e. operational occurrences are:

A.

To. furnish of therecords plant. of radiation levels in specific 1 areas B.

To warn of material radioactive uncontrolled in theor inadvertent movement of plant.

C.

To provide local and remote indication of ambient gamma radiation and local and remote alarms at key points where substantial change in radiation levels might be of immediate frequenting the area. importance to personnel e

e 12.3.4-1

. . _ _ = . - _ _

. Paoensen Gu a'ac es Insert "B" The Area SufIding Raawaste Rad 15 tion (ARS) Monitors (ARM) installed in the Alternate ARB during processing of liquid radweste. monitor radiation levels in and around these ARM's is described in section 12.3.4.1.10 The design objectives of !

1 4

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_ Peoponen (maar-E4 --

VEOP-FSAR-12 .

I.

Decontamination ARE-OOO9A Station (Large Parts) Area Monitor To continuously indicate the radiation levels in the

, A high alarm alerts personnel in the area of aarea a 4 deteriorating radiological condition.

' J.

Decontamination ARE-00098' Station (Small Parts) Area Monitor To continuously indicate the radiation levels in the A high alarm alerts the personnel in the area of aa .

deteriorating radiological conditica. .

K.

Instrument ARE-OOO9C Decontamination Station Area Monitor .

To continuously indicate the radiation levels in the e area alarm high aroundsignal the instrument decontamination alerts personnel working instation.

the a of a deteriorating radiological condition.

L.

Technical Support Center Cathode Ray Tube (CRT)

Display Room Area Monitor ARE-50002A To the continuously CRT display room. indicate the radiological condition of A high alarm signal provides l warning to the CRT display room personnel of a deteriorating radiological condition.

M.

Technical Support' Center Work Area Monitor ARE-500028 To the continuously work area. Aindicate the radiological condition of i

high alarm signal provides warning l to the work condi_

radiological area personnel tion. of a deteriorating i

l*$nserS 0 12.3.4.1.( Range a5xl iYsetpolrits ~ '

The range, setpoints, and control function of the PERMS area monitors are given in table 12.3.4-2.

Radiation zones for VEOP are described in table 12.3.1-1.

With the exception RE-0005, RE-0006, M area -0011 monitors RE-OOO2, RE-COO 3, RE-0004, located in radiat n Zones I o 11 I.

of the area monitors are l

l and ARE- 16a54 i m-12.3.4-6 i

i I__-__-______-_____ __ _ _ ...__ - .. _ . - ~. _ ....- .

e Pro r essr3 Gs4*;aes J

Insert "C" N. !

Alternate'Radweste Building Arei Monitor ARE-16861 To continuously west. indicate the radiation levels on the outside wall of the ARB.

4 area of a deteriorating radiological condition.A high alarm alerts p

, O.

Alternate Redwaste Building Area Monitor ARE-16862 of the shield well on the east side of the ARB.To e

A high alara con alerts personnel in the area of a deteriorating ' radiological condition.

P. l Alternate Radweste Building Area Monitor ARE-16863

\

To continuously area of the ARB. indicate the radiation levels in the dress-out a deteriorating radiological condition.A high alarm alerte personnel in th Q.

Alternate Radweste Building Area Monitor ARE-16864 s

To continuously indicate the radiation levels in the ARB A high alara alerts radiological personnel in the area of a deteriorating condition.

G

. v.

t 9

Paseossto Ca.uuaes _

VEOP-FSAR-12 The controf,'roo's monitor RE-0001 and the technical support center monitors, ARE-50002A and ARE-50002B, have greater I sensitivities than the other area monitors, since they are {

located in RE-0005, Zone I radiation areas; monitors RE-0002, 1 e During plant shutdown including refueling operationsand , the R

radiation than level on and above the operating deck should be less 2.5 mR/h.

i i

design basis accident,Thea high LOCA.

and of the range is dictated by the Each area monitor has two alarm setpoints, high. (See table 12.3.4-2.)

function, intermediate and i.e.,

RE-0002, RE-0003, RE-0005,If anda monitor RE-0006, has thea control alarm setpoint. control function is triggered coincidentally with the high s An intermediate alarm gives a visual indication radiation levelinhas thereached control theroom and near intermediate the detector that setpoint.

alarm gives both a visual and audible indication near theA high detector the control (along room)with a visual indication and annunciation i n '

reached. that the high slarm setpoint has been j.

L For testing, 7

?;

each area monitor has a check source assembly which is operated from the control console and uses a sealed Sr-90 source.

l Inservice inspection, calibration, and I

maintenance 11.5.2.5. of' the ARMS monitors is discussed in paragraph Iusaev " D" 12.3.4.2 Standard Raview .

la Evaluation American Nuclear Society (ANSI /ANS) HPSSC-6.8.1-1 . Design of the VEGP ARMS HPSSC-6.8.1, began prior to the issuance in 1981 of ANSI /ANS Location and Design Crits;ria for Area Radiation Monitoring Systems for Light-Water Nuclear Reactors, and initial design stages.therefore the standard was not specifically addresse other applicable, regulations and quides.However, the MMS is in conformance w 12.3.4.1.) ~

(See paragraph 1 Criticality not included monitors as defined in the VEGP design. in the Standard Review Plan are the design of the fuel pool racks precludes criticality underParagraph 12 all postulated criticality normal monitors are and notaccident needed.conditions and that therefore this 9.1.2, and subject is given in subsections 9.1.1, New Fuel StorageSupporting info ,

Criticality of the Reactor During Refueling. Spent Fuel Storage, an 12.3.4-7 Amend. 1 11/83 l

l

"jbaposen C H Au c,es *

.' Insert *D'_

12.3.4.1.10 Design objectives fer the ARS Area Radiation Monito rs The design obhectives of the AR3 J UI's durig normal 11guld radwaste processing and anticipated operational occurrences arer A. (

,8 To warn of uncontrolled or inadvertant movement of radioactive material in and arcund the ARS.

, B.

To provide local and remoto (in the ARS cont levels in and around the ARS.

c.

and radioactive leake in the ARS.To annunciate and warn o

D.

To furnish information for making radiation surveys.

By meeting the above objectives, the ARM's aid Realth Physica personnel achiavable (ALARA). in keeping radiation earposures as low as reasonably 9

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