ML20151Q711
| 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) | |
Text
2 Georgia FDwer Company F0st Ofhce Box 282 i
o' Wrrnesboro, Georgia 30830 Telephone 404 554-9961 404 724-8114 Southern Company Services, Inc Post Ofhce Box 2625 B:rmingham, Alabama 35202 Vogtle Project w phome20sa' " "
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 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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VEGP-FSAR-1 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.;
Level 1 el 220 ft O in. to 246 ft 0 in.;
Level 2 i
el 246 ft 0 in, and Above 1.7.1-1 Legend for Electrical Drawings 1.7.1-2 Legend for Control Logic Drawings J
1.7.1-3 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 1.2.2 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, maintenance building, plant entry and security building, a
vehicle.-.intenance facility, intake and outfall structuras, boathouse, chlorination facilities, fire pumphouse, demineralizer building, ield support building, the nuclear lIl25 trainingfacilitN.,a.*/ssalternate radwaste building g au/
g da y un m j
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 designed to provide protection as required frem floods, l
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 and orientation of the buildings on the site are shown in figure 1.2.2-1.
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
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VEGP-FSAR-1 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 processshields,bprocessskids,1 f
dry u::t; mae;;t..,
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Th(e circclating water cooling tower is a concrete, Wsitr D 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.
The nuclear service cooling water towers, shown in figure i
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 l
Unit 1 protected area, and to ensure that no construction 3
condition for Unit 2 affects operation of Unit 1, the following measures are taken:
I' Amend. 25 9/86 1.2.2-3 Amend. 35 3/88 i
l
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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i 6-02129-35 i
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VEGP-FSAR-1 Power b' lock entry (control' building).
e Control room (control building).
e Control building support facilitiss (locker rooms, e
showers, health physics office, laundry, first aid station, etc.),
Radioactive laboratories (control building).
e e
Communication room (service building).
e
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Technical support center (control building).
e Hot machine shop (auxiliary building).
e Hot instrument decontamination shop (auxiliary e
building).
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Drum storage area (auxiliary building).
e e
New fuel pit (fuel handling building).
Spent fuel cask handling areas (auxiliary and fuel e
handling building).
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Radwaste transfer building, e
Radwaste solidification and' volume reduction area o
(radwaste building).
Alternate radwaste building.
l e
l Water analysis room (turbine building).
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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.
f 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, T/, a-Ory Ac fi+ss Wais buo */di4 HVK p <wess4j 7
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TABLE 3.2.2-1 (SHEET 90 OF 97)
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_end Components Unit s unit 2 _SuppIV Crovo C46ss 9 t*9ery Desiensto_r tion Codt Q-tist Belated Desionator Comments
- 29. Turbine gener-S MA 6
2 C
AISC-69.
N N
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- 30. Store drain U8C-76 5
MA 6
2 C
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N System (Note Y)
- 31. River makeup S
NA 6
2 C
AWA C-200 N N
water piping 32, Radwaste 8
NA 6
2 C
AISC-69, N
N solidificatson bu6iding ACI 318-71,
- 33. teSCW tower UllC-T6 8
NA 0
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AISC-69, Y
Y valve house
- 34. Radwaste ACB 318-71 gj 8
NA 6
2 C
AISC-69 N
N og t rans fe r buiIding ACI 388-71 g
- 35. Category I USC-76 evj 8
NA 0
3 C
AISC-69, Y
Y Note 2 electrical (f) cable tray A8SI-68 pe supports pg
- 36. Category 1 I
8 NA 0
1 C
AISC-69 Y
Y W
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- 37. Ca tego ry 1 8
pipe stepports See Note 4 AISC-69 Y
V Note 2
- 38. Pipe whip 188-NF W,8 NA 0
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- 39. Water tight I
8 NA 0
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- 40. waterprooring '
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- 41. Category I 8
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Centrol Sasildig - Level 4 sternel caselled 8,000 3
7,000 8
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rae. 9.s.5-5 wter pumps (e6eet 253 odeic-Alternate h ete ensl8 ding s
'Aleermate 38,948 S
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Georgia Power d n,'M"?,3l%r"t'" "
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Amesut. 19 9/05 Amend. 25 9/06 MW REW. 4 m,
AUXILIARY BUILDING AND g
Re en ree naser MISCELLANEOUS DRAINS FIGURE 9.3.3-3 (SNErl 11 OF 11)
E J
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VEGP-FSAR-9 mechanisms to allow chiller opera' tion down to approximately 10 percent of its capacity.
9.4.3.3.2.3.7 Radwaste Solidification Building Elevator Machine Room.
outside air supply system that provides fresh air,The elevator m heated as required, to the elevator shaft under positive pressure.
elevator machine room is supplied with outside air from anThe intake plenum at el 263 ft 6 in.; air is exhausted to the atmosphere at el 263 ft 6 in.
This system assists in minimizing exfiltration from the radwaste solidification bui1 ding.
9.4.3.3.2.3.8 Health Physics Building.
The 100-porcent outside air supply is filtered and conditioned by the air Supply air conditioned to 55'E is delivered to the different Each zone is equipped with an electric reheat coil zones.
controlled by a space thermostat.
duct is initiated when the spaca relative humidity becomes lower than the preset value of the spece humidistat.
An air exhaust fan collects all room air and discharges it to the atmosphere at el 237 ft 0 in.
9.4.3.3.2.3.9 Alternate Radunate Building.
Continuous manual ridge ventilators are provided for the alternate radwaste building.
the vendor-supplied container vent system to exhaust theA vent l building filtration system.potentially contaminated process air through the Provisions are included to exhauct 25 air from the radwaste tunnel area and portions of the radwaste transfer building through the auxiliary ha41 ding flitration system prior to completion of the radwasta solidification bugidina.
c37vsstrT l
9.4.3.3.3 Safety Evaluation
/
Since there is no safety design basis ror the radwante solidification building and'radwaste transfer building ventilation system, no safety evaluation is required, a a w. m y a s,,, u, /
l 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) and recirculates the air through high efficiency particulate (HEPA) 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.
2
,y
Peaease.o du a xe. e4
'i VEGP-Ir.MR-9 5-TABLE 9.4.3-6 (SHEET 4 OF 4)
{
Health Physics Building 'WAC Supply Air Handli'ag Unit Quantity Fan capacity ft1/ min) 1 Static pressur(e (in. WG) 2300 8
Fan (hp) 2.75 Coolir# capacity (5tu/h) 2 5
Heating capacity'(kW) 196,000 Filter efficiency (%)
35 l
80 to 85
.J Alternate Radueste Building Control Room and Drese-out Area Air Head 11ag Unit Quaataty
?
0 1
Faa Capacity (ft /nla) 1000 Static Pressure (la. NO)
Faa (MP) 0.70 0.78 Cooling Capacity (BTU /N)
I i
Heating Capacity (KW) 65,000 I
17 Filter Efflolency(*)
l Low Alternate Radusste Su11 ding Control Room api Dress-Out Area
/
i condensing Unit b
i f
Quantity 1
\\
Capacity (BTU /N)
Refrigerest 68.000 R-23 Fan Noter (W) k 0.6 F *--
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A.
.imcation: _R****** Transfer h 11dinam-l L
2 y,avais 1, l
E.
Figuress.
y sa, ErRL 7A j
c.
Descriptions includes fire zones 3005, 301, 304, 303, e
30{554]
m... 1 -.. J. ~
1
~ L M=-
sL t
D. (pescnytson is- _
6detinsgarnf e,atte 4
1.
Level 1 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,
- Unrated exterior area boundary.
i
~ 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.
il' 7
South
- Unrated exterior area boundary.
2 h ::t:d i ::12:n vy l
- :::ts:
- D
- = ' ! r. *'..%
East
- Unrated exterior area boundacy.
j West 3
.- 2-h rated barrier separates from stairwell No. A.
I
- Unrated exterior area boundary.
E.
Area Access a
1.
Level 1 North Class A door from 1-AS-L1-0.
j-f-West Class A door from stairwell No. 44 c3 East
~ 7nrated rom outside.
Elevation 237 ft - 0 in.
(
g 2.
East Unrated door from stairwell No. C.1 1$
24 3.
Level 2 g
West
- Class A door free stairvell No. A. I g
F.
Scaled Penetrations a
Seals meet or exceed fire barrier ratings.
G.
Fire Dampers f$
Fire dampers meet or exceed fire barrier ratings
{
j b
SIhfeShute;.g. Components H.
t l
i e
I Sa'fety-Related Equipment I.
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 dee==* en11actina tanh*_
pumps
" f,
& 6MPM K.
sudl 1.' Zone No. 3005 Fixed combustible quantities Cable insulatio i
hypalon value) n (equivalent Charcoal 0 lb Cellulosic materials 0 lb j
Oil / grease 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 materials 0 lb 1'
Oil / grease
- 0. Ib Plastics 0 lb Rubber goods 0 1h 0 lb Heat release i
. Fixed combustibles
..i
'fransient combustibles O Btu 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 materials
~"
oil / grease 0 lb Plastics 0 lb
'l Rubber goods '
0 lb O 1h Heat, release Fixed combustibles,
Transient combustibles 5,003,260 Stu 800,000 Btu i
Combustible loading 24,281 Stu/ft8
+
re severity (wood equivalent) 18 min L.
Eva us on of safe Stnitdown capability J
1.
For a fire in this area, use safe shutdown Tr i or S.
anA 2.
Special operational and design consideration s
None.
d 3.
Spurious actuation considerations:
Non..e.
15 24 M.
Fire D;etection Early warning fire detectors are installed within th following zones:
e Zone 3003 Zone 301 3
(,,
same so. ase
. rises esen'aatte essoasues s
Cable Ea'r = (ega. 1lvalems a
asset Celteneese notettait.
os vessees 7890 14 Plaettes soo1m I
hebber gases Seelh 440LD ames rStones M hMehlM e
,. Tremotest eseestah&as l
kosaheettuatoediae
- ' ris..meser tvees ses,etect
@'ft*
19 ass Amend. 15 3/85 Amend. 24 8/84 9A.1.129-5 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, Zone 302 - No sone coverage.
j Zone 303 - No sone coverage.
_ _ 3an.
1oL -
i ' 3*44 ~Sto ; Q as causea w WarhitihmTMM 5M "MA, 2.
aema covannsa
= :2:
Hose stations (with portable extinguishers) ar 5
24 conveniently located to each area.
e can be reached with at least one effective w Any location i
stream.
2
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1.
o
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Amend. 15 3/85 Amend. 24 6/06 9A.1.129-6 Amend. 28 11/86
~
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Peoeosab CH A tmes VBGP-FSAR-9A i
i I
i 0.
Radioactiva Materials
(
Raittoective liquids.
F.
lation
.eeks can be removed using the neraa.
aystem in a omeo-through only mo l ventilation areas isolated by fire dampers, de of operation.
l yor i
portable fans using fleaible tubes to direct the smokesmoke
{
to an area capable of being ventilated or directly t
~
outside.
o i
Q.
Drainage Secause there are ne safe shutdown and safety-related components in this area /or consideration has been gives to fleeding.
, ne specisi Einergency Lidting R.
8-h-rated battery fixture (s) provide safe ingress /
i ogress of personnel.
S.
Deviati,ons and Just11.esticas NN 1.
Unrated asterior fire area wMan:
See Appendia 93, section C.S.a(1).
V N
f.a4;..4.vedrywaste t
Let>1evel intermediate-level radiometive waste in i
solidtfica*4em material, which in tura is in motst g,,
Solid low-level radioastive waste.
- ^
Amend. 15 3/85 Amand. 24 6/84 gn.1.123-7 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:
scription:
Includes fire mone 330 t
Al raate radwante building (one level 230 t.S in.)
ructure, el D.
Descri tion of Soundaries i
Floe
- Unrated concrete be mat.
Ceili
- Unrated exterior boundary.
North 3-h-rated barrie 1-RTS-L1-A.
separates area free
~
West ated exteri r area boundary e
south
- Unr ted este or area boundary.
n.
East
- Unrat sa rior area boundary.
E.
Area Access O
East - Unrated outside.
Wsat - Unrated rf outside.
- Unrat roll-up r from outside.
l F.
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 3
t Fixed combustible quantities j"
I cable insulat:1on (equival hypelon value)
Charcoal 0 lb l
ellulosic natorials 0 lb a
,1/ grease 5570.lb l
P; stics 1600 lb r goode 0 lb 0 lb Heat to ase
.. 1' Fixed stib e
76,560,000Staa'j6 Transi tc tibles 77,360,000 at:4 i,.
Catbustible e
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 led within the c11owing nonr!.:
- Zans 330 t
9 a'
t 9A.1.131-2 Amend. 28 11/86
~
Peopme t'MAMER VEGP-FSAR-9A
., Fire suppression
'g
'1.
Automaelc Zone 330 proaction sprinkler system - P ial zone coverage.
2.
Marical e
e rtable eatinguichers are convenient a
area.
located in o.
Radioac ve Materials Radios inve liquids d
1 Radiacti drywaste Low-level termediate-level adioactive vaste in solidificat..
- material, in turn is in meta)
/
)
Solid low-leve radtonct waste.
P.
Ventildtion g,
Smoke can be removed 13 tubes to direct the portable fans using flexible outside.
Q.
Drainage Because there are safe safety-related e tdown ara /or nents i been given to flooding.this fire arma, no spe consideration R.
Emergency Li ir.g 8-h-rated tery fixture
)
se of peruonne(l. pro de safe ingress /
S.
Deviatto and Justifications o Var exterior fire area bounda 5
Appendix 95, section C.5.t.(1).
t e'
9A.1,131o2 Amend. 28 11/86
PReph CWAMAES l
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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
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 FLOOR PL1_M EL. 237'-O
FIGURE 9A-43 i
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hM kTano h mend. 25 9/84 FIRE'ARe 8 RADMASTE -
new.a TIUuSSFER BLDG. LEVIL II FLOOR PIJul EL. 247'-0" FIGURE 9A-44 L
4 VEGP-FSAR-ll
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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 all plant conditions (section 11.W (s.4). Ay//,vrtaasNee), wad M
/
42 fav%'kes m jmwded is pneese n.ed s hee, 94 esHoe r
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.
oe o Hvaf,kr*k 11.4.2.3.10 Packaging, Storage, and Shipment pedry kyj Solidified wastes, spent filter cartridges, and soli compactible wastes are packaged in 55-gal drums accordance l19 with 49 CFR 173.395(a)(1) and shipped in shielded casks, as 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 storage for low level solid radwaste contains 992 ft area 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
11.4.2.4.2 Portable Radwaste System 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.
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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
VEGP-FSAR-ll 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 25 appropriate shielding is available.
Onsite storage for decay of short-lived radionuclides is accomplished both prior to i
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
A Page 1 of -
INSERT A
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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 material, radioactive and non-radioactive waste.
i 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
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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 11.5.2 SYSTEM DESCRIPTION 11.5.2.1 Digital Radiation Monitoring System The process and effluent radiation monitoring system (PERMS) based on a distributed digital microprocessor approach, where is each radiation monitor is self-contained and consists of a detector and a data processing module (DFM) that contains the microprocessor.
The DPM is the basic control center for each PERMS channel.
Each complete channel consists of a monitor with power supply and preamplifier; a local dedicated data d
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 the field-mounted detectors on a CRT and hardcopy printer j on demand.
This is accomplished by either the communications console or the safety-related display console (SRDC) located in-
?
the control room.
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 Table 11.5.2-2 lists the detectors used in the PERMS.
4 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 11.5.2-5 gives the the detector locations.
Figure 12.3.1-3 shows 5 11.5.2.3 Moni tor Functions 7
jg-The PERMS con ts of 23 area monitors process and effluent moni 8 per unit and 7 shared),
(27 for Unit 1, 28 for Unit 2, rs (subsection 11.5.2) and shared), 20 post-accident monitors (subsection 11.5.5) (10 per unit),
passive activity collectors (5 per unit) planned forincluding 10 3
installation at the VEGP site.
areas of the site that are common to both unite.Some monitors
]
5 monitors are identified by an "A" in front *of the monitor's tag These i
number (i.e., ARE
).
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 activity releases from the plant vent are below specified limits.
The monitor also se'rves as a backup to the t
containment vent particulate monitor RE-2565A.
i
. Since the main plant vent discharges directly to the atmosphere, the data from this monitor are i
l most representative of particulate activity releases to the plant environs.
Should the t
activity exceed a specifAed level, a high radiation level alarm will be annunciated to indicate that an increase in particulate release has occurred.
The specific source of release i
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 activity is filt6 red and routed to the plant where it is again monitored by the plant
- vent, vent monitors RE-12442A, B, and C prior to discLarge to the atmosphere.
In the event of a fual handling accident inside the fuel handling building, ARE-2532 and ARE-2533 are capable of l
detecting the high activity in order to switch the 8
1 fuel handling building ventilation system from the normal operating mode to the accident mode, which i
includes safety-related filtration units.
i subsection 9.4.2.)
(See 23.
ARE-50003 - Technical Support Center Air _ Intake J
Process Radiogas 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 support center of a deteriorated diological 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 of a leak of radioactive water into the component cooling system.
11.5.2-10 Amend. 35 3/88
~.
Page 1 og }
INSERT C
- 24. ARE-13256 - Dry Active Waste Processing Building Effluent Particulate Monitor 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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These components include the recycle evaporators 1
and waste evaporators.
A high alarm signal provides operator warning so e
that action may be taken to avoid further radioactive contamination of the auxiliary steam condensate.
Remote readout is provided at evaporator steam l
supply system panel.
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 and high.4 When the radiation level being monitored reaches the antermediate setpoint, personnel of the monitor reading.a visual indication alerta plant If the high setpoint is reached, an alarm will be annunciated.
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
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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 ess sarety ctani-selseic tors Size /Page flog Automatic Dienster seonitor Classiri-col Guastri-per seoving (rte /
Contros sea te rie s,
Power sanni tor Twee g;ation Gada cation tini t filter han ment function schedule Susolv toaste cas Decay Iank a
fat-0039A and a
- Prucess, sesas esA seo 2
(C rer Unit 2 onsy) insene-Sue /
soone 136 in, soon-cla ss (unit s200(.
x 36 in.
It t) gunit :)
Assn 3
500/
AS2 7, (unit 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 Yes Common 32,700 Yes:
36 isa. x Cseas 31 m
AAE-2533A and a insane 3
l M
suitches 36 in.
tn buiseing Assa to acci-AS27 N
dont mode is gauge 8
or opere-V tion in-M cauding sarety-reseted restration mai t s lechnical Support 2* >
Center SU Amt-50003 S8
- Process, seses esA seu Gammon 1200 sect.e 20 in. x IJun-C s a s s DU insine OO Its in.
If dieses AslM backed AS2K L.s UI tah 18 gauge ZFSE"rp
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?ABLE 11.5.2-1 (SHEET 4 op 7) 3 me i
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TABLE 11.5.2-2 (SIIEET 2 OF 3)
Radiation Menetor Detector lone Detectable Lssatio.D Iv80 1fWI/hl _
Ms.ior. Isotoseg
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i Contro8 Hooo Air Intake Af-12886, R[-52337 Cosot rol room thin walled
<0.2$
Me-133, Xe-135. kr-aS. 2-133, 1.01-6 to I.ot-1 C-M tusnes t-133, Co-SS, 00-60 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 6-138, 4-133, Cs-134, Cs=331, 1.01-15 to 3.0[-6 solidife-scint488ation Co-SS Co-60 cation badg ARL-833338 isodine)
Radwesto Comea
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solider 8-scents 8fation cation b8dg M
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~H AE-0039A, S, and C Aum ktdg then watsed 0.2$-2.$
Me-t33 Me-935..kr-45 1.01-6 to 3.ut-1 C-M Eube 2.5-55 2.5-15 fuel Handling Su,8 ding Effguent "t*
AML-2532A and 8 s aaer s Ihnee w Iestd e s..",.*. S xe-133, Xe-135, Mr-SS 1.O(-6 to I.Of-l 3
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VEGP-ESAR'-11 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 l
'M
- Eshbbl>ed based o., b He 0 $$s,'le Oo.se Ghulakone/ Mone/
y Amend. 35 3/88
t
's VEGP-FSAR-11 TABLE 11. 5.2-5 (SHEET 2 OF 2 )
Control Equipme.nt Room Local Pathway
_. Number
_ Range a
Indication Indication Fuel handling AFE-2532 0-27,000 Yes Yes building AFE-2533 sf8/ min exhaustib>
Waste gas AFE-0014 0.2-2.0 Yes Yes processing' sf*/ min effluent' Oy AN64.
Aff")32S6 0~S0'O fes
.s 9 '/mo'n Wash rwestsy' f
b,L1 efLJ These pathways are not equipped with a release flowrate a.
measuring device due to the fact that radioactivity exceeding preset limits is not sent to the environs but instead to the j
respective waste processing systems.
b.
These pathways are also monitored downstream by the plant vent monitor.
0357V Amend. 5 4/84 feed Amend. 35 3/88 I
\\
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, _. _ _ _1188 as e.se.00 -
_TUAteNt 8.008 (16.000 t XHAUST CONTA44EMGNT 9U6L06800 gfgYcs 1
i 13.798 Aat seu ta 4 et b
i n ges "i".%
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- LANT vm aat stat la 4 $4
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13.000
,, a WASTE GA8 PMoctSetNG SYSTEM as este acessoa -
OTH.'R 900Act8-Usea m 4.= Q uw Wntrt BussPres-r 1
(
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ans uts:
w t. ca RAOWA878 34 esei12 4254 DutLDesse ta, g, cs M,_. -L-. 3.188 fume.
- L.tN.G.
tXHAUST i 880 CONTAl8804GNI uto. 0 Va, c....
WASTE SAs PROCasmess ta.s c pg 88 'se.i Uself 3 4
t.tes WSc pgggyyggy
,,,,3,,
800 at seasc OTHER SOURCES
- ALL PLOwAAf tg IN PT /h68M 3
O moNotoal#4 LOCAt'0*'s c, -
Ainend. 35 3/88 voogte PERMS NORMAL CASC'.lS EFFLUENT tts GeorgiaIbwtr i=4,ciar,atNamatimeo rtaNT RELEASE P4tilWAY iA=.U
,2
=
FICune 11.5. 2-ti
TABLE 11.5.3-1 (SalEET 3 OF 3)
Monitor Samose scentification ftund L9Catton lEne Purootg RE-12444A vent i sa t ion At monitor Passive RE-124448 air errsuent Provide qisantitative activety AE-12444C (gaseous pa rticula te release data.
Ca s ibra tion release pathway) ca rtrsdge of continuous monitors.
Passive iodine ca rtridge Radiogas 25 Vapor sample AAE-50003 Technical Technicas Radiogas and Determine isotopic activity support contar support conter Iodine
. \\
air intalie air intake in technica s suppert center A
following accident.
duct ARE-13256 PTW fr** ton 7 Af >.re lea.
(rua-> <deg,sc B- */A *=7 EHLauf 5,f,Qfe f,orsa(e p a.),k / u f* * "7) ~
,,j,,,,
,,7 y
Gt,u fou,,Ca..A:,asa.s ave. /,,,,
Q y
t m
3*
N sW H
I
/
3 Q..
Ittese monitors require saapilng in acCordertCe Witf a.
3 Regulatory Culds 1.21 25 z.
On
/
VEGP-FSAR-12 12.2.1.4 Stored Radioactivity The principal sources of activity not enclosed by the power block buildings are The refueling water storage tank.
i 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 e
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 cartridges, solidified spent resins, evaporator bottoms, and chemical wastes.
Radioactive wastes stored inside plant structures are shielded so that there is Zone 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.
12.2.1.5 Field Run Pipe Routing i
The procedures for routing of radioactive piping are discussed in paragraph 12.3.1.1.2.
I l
12.2.1-11 x
t
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.
This will assure that the dose rate at the site boundary is less than 1.0 mr/ year.
Interior cotcrete shielding is provided to limit exposure to personnci during waste a
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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_P=anaean Cuawass 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 and effluent radiation monitoring system (PERMS).
C.
Sampling system.
D.
Post-accident monitoring systems (PAMS) radiation J
monitors.
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 complia personnel radiation protection guidelines of 10 CFR 20 10 CFR 50, 10 CFR 70, and Regulatory Guides 8.12.
1.97, 8.2, 8.8 and The design of the fuel pool racks precludes criticality und all postulated normal and accident conditions.
er criticality monitors, as stated in 10 CFR 70.24 and Regulatory Therefore, Guide 8.12, ars not needed.
4 NSSST 12.3.4.1.1 Dssign Objectives The design objectives of the ARMS durir.g normal operatt g pl conditions and anticipated operational occurrences are:
ant e.
A.
To. furnish records of radiation levels in specific areas of the plant.
1 B.
To warn of uncontrolled or inadvertent movement of radioactive material in the 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 importance to personnel frequenting the area.
e e
12.3.4-1
-w=w""~"
. _ _ =
Paoensen Gu a'ac es Insert "B" The Area Rad 15 tion Monitors (ARM)
Raawaste SufIding (ARS) installed in the Alternate ARB during processing of liquid radweste. monitor radiation levels in and around these ARM's is described in section The design objectives of 12.3.4.1.10.
1 4
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_ Peoponen (maar-E4 VEOP-FSAR-12 Decontamination Station (Large Parts) Area Monitor I.
ARE-OOO9A To continuously indicate the radiation levels in the A high alarm alerts personnel in the area of aarea a deteriorating radiological condition.
4 J.
Decontamination Station (Small Parts) Area Monitor ARE-00098' To continuously indicate the radiation levels in the A high alarm alerts the personnel in the area of aa deteriorating radiological conditica.
K.
Instrument Decontamination Station Area Monitor ARE-OOO9C To continuously indicate the radiation levels in the e
area around the instrument decontamination station.
high alarm signal alerts personnel working in the a of a deteriorating radiological condition.
L.
Technical Support Center Cathode Ray Tube (CRT)
Display Room Area Monitor ARE-50002A To continuously indicate the radiological condition of the CRT display room.
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 continuously indicate the radiological condition of the work area.
A high alarm signal provides warning i
l to the work area personnel of a deteriorating radiological condi_ tion.
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 monitors RE-OOO2, RE-COO 3, RE-0004,
-0011 11 of the area monitors are located in radiat n Zones I o I.
l l
and ARE-16a54 i
m-12.3.4-6 i
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Pro r essr3 Gs4*;aes e
Insert "C"
J N.
Alternate'Radweste Building Arei Monitor ARE-16861 To continuously indicate the radiation levels on the outsid west. wall of the ARB.
area of a deteriorating radiological condition.A high alarm alerts p e
4 O.
Alternate Redwaste Building Area Monitor ARE-16862 of the shield well on the east side of the ARB.To con e
alerts personnel in the area of a deteriorating ' radiological A high alara condition.
P.
Alternate Radweste Building Area Monitor ARE-16863
\\
To continuously indicate the radiation levels in the dre area of the ARB.
a deteriorating radiological condition.A high alarm alerte personnel in t ss-out Q.
Alternate Radweste Building Area Monitor ARE-16864 To continuously indicate the radiation levels in the ARB s
high alara alerts personnel in the area of a deteriorating A
radiological 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 Zone I radiation areas; monitors RE-0002, RE-0005, During plant shutdown including refueling operationsand R 1
radiation level on and above the operating deck should be less e
the i
than 2.5 mR/h.
design basis accident,The high and of the range is dictated by the i
a LOCA.
Each area monitor has two alarm setpoints, high. (See table 12.3.4-2.)
intermediate and
- function, i.e., RE-0002, RE-0003, RE-0005,If a monitor has a control alarm setpoint. control function is triggered coincidentally with the high and RE-0006, the s
An intermediate alarm gives a visual indication in the control room and near the detector that radiation level has reached the intermediate setpoint.
alarm gives both a visual and audible indication near theA high detector (along with a visual indication and annunciation i the control room) that the high slarm setpoint has been n
j.
reached.
L 7
For testing, each area monitor has a check source assembly
?;
which is operated from the control console and uses a sealed Sr-90 source.
Inservice inspection, calibration, and maintenance of' the ARMS monitors is discussed in paragraph l
11.5.2.5.
I Iusaev
" D" 12.3.4.2 Standard Raview la Evaluation American Nuclear Society (ANSI /ANS) HPSSC-6.8.1-1 the VEGP ARMS began prior to the issuance in 1981 of ANSI /ANS Design of HPSSC-6.8.1, Location and Design Crits;ria for Area Radiation Monitoring Systems for Light-Water Nuclear Reactors, initial design stages.therefore the standard was not specifically addresse and other applicable, regulations and quides.However, the MMS is in conformance w 12.3.4.1.)
~
(See paragraph 1
Criticality monitors as defined in the Standard Review Plan are not included in the VEGP design.
the design of the fuel pool racks precludes criticality underParagraph 12 all postulated normal and accident conditions and that therefore criticality monitors are not needed.
this subject is given in subsections 9.1.1, New Fuel StorageSupporting info and 9.1.2, 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 Monitors 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 in keeping radiation earposures as low as reasonably achiavable (ALARA).
9
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