ML20205C141

Forwards Proposed Changes to FSAR Text Documenting Incorporation of Alternate Facility in Design.Drawings Will Be Available in 2 Wks.Proposed Changes Will Be Incorporated Into Amend 25 to FSAR Scheduled for 860919

ML20205C141
Person / Time
Site:	Vogtle
Issue date:	08/06/1986
From:	Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
GN-1033, NUDOCS 8608120261
Download: ML20205C141 (36)

Text

Georgia Power Company Pbst Offico Box 282 Waynesborn Georgia 308tD Telephone 404 554-9961 404 724-8114 Southern Company Services, Inc.

Fbst Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 VOgtle Project August 6, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention:

Mr. B. J. Youngblood Log:

GN-1033 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.

20555 REF: CONWAY TO DENTON, GN-972, 5/29/86 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 ALTERNATE RADWASTE BUILDING

Dear Mr. Denton:

In the referenced letter an overview was presented of the Plant Vogtle alternate radwaste system. Attached are the proposed changes to the FSAR text which documents the incorporation of an alternate facility in the VEGP design. The drawings (FSAR Figures) are still being processed and will be made available for your staff's review in approximately two weeks. The proposed FSAR change, to include figures, will be incorporated in Amendment 25 to the FSAR scheduled for September 19, 1986.

Should you have any additional questions, please inquire.

Since rely, b-J. A. Bailey Project Licensing Manager JAB /sm Attachments xc:

R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector I

J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey M. A. Miller (2)

L. T. Gucwa B. Jones, Esquire Vogtle Project File l

G. Bockhold, Jr.

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1.2.2 FACILITY ARRANGEMENT t

The principal buildings and structures associated with the plant include the containments, the equipment buildings, the

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turbine building, the auxiliary building, the control building, 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.

Ancillary structures include the administration building,

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warehouse building and receiving facility, service building, I

maintenance building, plant entry and security building, vehicle maintenance facility, intake and outfall structures, boathouse, chlorination facilities, fire pumpho 4

demineralizer build ngt_fie d u

din,

he nuclear training facilit ; AND ALTERNATE RADWASTE BUILDI These buildings and structures are founded upon suitable 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

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designed to provide protection as required from floods, I

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tornadoes, earthquakes, and the failure of equipment producing flooding, missiles, and pipe breaks.

Additional discussion of design considerations is provided in chapter 3.

Location and o'rientation of the buildings on the site are shown in figure 1.2.2-1.

The general arrangement of the power block 1

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-Jfsb5 The containment, shown schematically in figures 1.2.2-31 and 1.2.2-32, encloses the reactor coolant system, the steam generators, some of the engineered safety features systems, and

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supporting systems.

The functional design basis of the Seismic Category 1 containment, including its penetrations-and i

isolation valves, is to contain with adequate design margin the l"

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

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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 equipment building, shown in figures 1.2.2-17 and 1.2.2-18,

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provides protection from the weather for equipment located l

within the building.

The equipment building consists of l

1.2.2-1 i

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VEGP-FSAR-1

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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),

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serves as a collection tankage area, providing waste holdup and pumping capacity,necessary to transport the liquid and slurry s.

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

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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 circulating water cooling tower is a concrete, natural draft, hyperbolic structure.

The to'wer is designed to dissipate all excess heat removed from the main condensers and accomplishes this function by the use of the spray network, the tower basin, and c'irculating water pumps, piping, and valves.

The intake structure houses the circulating water pumps,

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turbine plant cooling water pumps, and associated auxiliary equipment and piping.

The nuclear service cooling water towers, shown in figure 1.2.2-30, are Seismic Category 1 concrete mechanical draft structures.

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 sink.

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,

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to prevent unauthorized construction personnel from entering key operating areas, and to ensure that no construction condition for Unit 2 affects operation of Unit 1, the following measures are taken:

A.

Physical separation of Unit 1 from Unit 2 is provided.

B.

Prior to the start of operation of Unit 1, electrical, ventilation, and process systems in the construction area of Unit 1 are segregated from similar systems in the construction area of Unit 2.

C.

Access between the unit under construction and the

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operating unit is controlled.

1.2.2-3

5 rNSF2 T THE. AL TERNATE RADWAS TE.

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s D.

A temporary partition exists in the control room to separate the Unit 1 portion from the under-construction Unit 2 portion.

E.

Shared systems and interfaces between units are

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isolated from Unit 2 and/or completed and checked out for Unit 1.

1.2.2.1 Units 1 and 2 Shared Facilities The following facilities are shared by Units 1 and 2; the locations are noted in parentheses:

o Plant access control (plant entry and security building).

Power block ent'ry (control building).

e e

Control room (control building).

e Control building support facilities (locker rooms, a

showers, health physics office, laundry, first aid 13 station, etc.).

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e Radioactive laboratories (control building).

e Communication room (. service building).

e Technical support center (control building).

e Hot machine shop (auxiliary building).

e Hot instrument decontamination shop (auxiliary building).

e Drum storage area (auxiliary building).

e New fuel pit (fuel handling building).

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

e Radwaste transfer building.

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e Radwaste solidification and volume reduction area LEAg Qaste ALTERNATE RADWASTE SulLDING,

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ne building).

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Nitrogen storage area (outdoors).

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l TABLE 3.2.2-1 (SHEET 90 OF 97) l (d)

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Codes and Prencipal (i)

Environ-S tateda rd s Construc- (h) 5.efety mental (k)

Prencipal System Location Source of Qu.e l i ty SafYty Se e ssic and Components Unit i Unet 2 Supply

_Cro m Class Capny Oc_se30_r t e nn Code Q-Li st Rela ted Des eana tor Comments S

NA 6

2 C

AISC-69 N

N

29. Turbine gener-ACI 318-71 ator pedestal UBC-76 I

S NA 6

2 C

AWA C-200 N N

30. Store dra in (Note Y) system 3 15 I

31. River makeup S

NA 2

C AWA C-2OO N N

6 water pipeng B

NA 6

2 C

AISC-69 N

N

32. Radwaste ACI 318-71 soliderication Unc-16 building S

NA u

I C

AISC-69 4

Y 0

33. NSCW tower ACI 318-71 8

NA 6

2 C

AISC-69 N

N valve house 3N. Radweste ACI 318-11, t ransfe r U6C-ib

35. Category 1 8

NA O

1 C

ASSC-fi9 Y

Y Note 2 building.

AISC*b6 39 electrecal cable tray B

NA U

1 C

AISC-09 Y

Y Note 2 3

l supports

36. C.stegory 1 HVAC duct Note 2 g

suppo rts W. 84 NA to 1

C AISC-69 Y

Y g

37. Pape stepports g

38. Pepe whop H

MA te I

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Y e.rj restraants (f}

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39. Wa ter t eglit C

m t'q N

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doors and scals lt NA f.

40. Wa te rp rnor s nq f

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41. Category 1 0

NA 18 1

C Y

Y and water stops td

42. Category 1 0

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NA to 1

C AISC-69 Y

Y bachteIl tank liner 3

S NA sa C

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y plate 8e3. Underground ACI LIS-Il l

Category 1 m_--~-

pepen, and B

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nechanical C

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notors C

C n

Ma s.

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NinA mci Y

N Noto an components J

msg Y

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B NA 6

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Instrumentation OO $SQ and controls UU U D'D 0 0* 4 4.Q.

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co co co co cn t#8 Ut A A A

VEGP-FSAR-3 Wt*Nw*Wm Wt*Ww + 0. 5 Wp + W,

,{N where:

j Wt = total tornado load.

W,= total wind load.

Wp = total differential pressure load.

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Wm = total missile load.

The maximum pressure drop of 3 psi, applicable to a nonvented structure, is used for W unless a lower value is justified using the provisions of Se,ference 1, for partially vented structures.

When the tornado loading includes the missile load, the structure locally may go in the plastic range due to the missile impact.

The procedure for analyzing local missile effects is presented in appendix 3C.

The analysis of the nonsafety-related equipment building shows that it will not collapse on adjacent Seismic Category 1 structures, equipment, systems, or components due to tornado s

loading.

1 3.3.2.3 Effect of Failure of Structures or Components Not Designed for Tornado Loads The non-Seismic Category 1 structures, equipment, systems, and components not' designed for tornado loadings are investigated to ensure the following:

A.

These structures, equipment, systems, and components cannot produce missiles that have more severe effects than the tornado-generated missiles discussed in para-graph 3.5.1.4.

B.

Their failure will not affect the integrity of adjacent Seinmic Category 1 structures.

This design ensures that Seismic Category 1 structures, equipment, systems, and components required for safe shutdown i

after a tornado will rform thair_i_ntended_ functions.

M0 Al TE!6 LATE MADHIASTE BU/LD/A!6 The analyse f the turbine Jding, radwaste transit building, amt radwaste tunne (Seismic Category 2 structures) show that t ey will not jeop dize adjacent Seismic Category 1 structures when subjected to the tornado loads described in paragraph 3.3.2.2.

3.3.2-2

]j VEGP-FSAR-3

.3.7.B SEISMIC DESIGN

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All structures, systems, equipment, and components related to plant safety systems are required to have the ability to i

l withstand potential-earthquakes.

Each structure, syste.m, cquipment, and component is placed in the applicable seismic category, depending on its function.

A two-level system is used for the seismic classification of structures, systems, and equipment of the facility.

A definition of the seismic classifications and a listing of structures, systems, and

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cquipment are included in table 3.2.2-1.

Seismic loadings are characterized by the safe shutdown earthquake (SSE) and the operating basis earthquake (OBE).

The SSE is defined as the maximum vibratory ground motion at the plant site that can be reasonably predicted from geologic and seismic evidence.

The OBE is that earthquake which, considering the loca.1 geology and seismology, can be reasonably expected to occur during the plant life.

All Category 1 structures are designed for SSE and OBE condi-tions.

Category 2 buildings are designed using the Uniform Building Code, 1976 edition.

In addition, the radwaste and de s tMAT transfer building, the radwaste transfer tunnel, M the radwaste solidification buildingJpre designed to withstand the. or WK ALTEHAt-OBE event.

Category 2 structures, -systems, equipment, and ggwag7y ggtag components, whose failure could result in the loss of required safety functions of adjacent Category 1 structures, systems, equipment, or components shall be either separated by distance or barrier from the affected structure, system, equipment, or component or investigated for SSE loadings to ensure that their failure will not impair the safety-related functions of the adjacent Category 1 structures, systems, equipment, or components.

For Westinghouse-supplied items, refer to section 3.7.N.

3.7.B.1 SEISMIC INPUT The seismic criteria for VEGP are developed by the Geology Department of the Hydro and Community Facilities Division of the Bechtel Corporation in San Francisco.

k The plant site geologic and seismologic investigations are covered in section 2.5.

Based on this data, the peak ground accelerations for SSE and OBE are established as 0.20 g and 0.12 g, respectively, as discussed in subsection 2.5.2.

a 3.7.B.1-1

VEGP-FSAR-9

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D.

The safety-related Seismic Category 1 spent fuel cask bridge crane and fuel handling building ensures that fuel handling and storage systems, structures, and components are designed for adequate safety during l

normal and accident conditions.

E.

The design and operation of the OHLHS is such that the design features of the OHLHS, i.e, single failure proof, or the consequences of a failure are acceptable to ensure the capability to safely shut down the plant,

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remove decay heat, and maintain doses within prescribed limits.

F.

The OHLHS conforms with the applicable portions of codes and standards invoked for the OHLHS design, operation, inspection, testing, and maintenance.

G.

Crane operators shall be trained and qualified and conduct themselves in accordance with Chapter 2 and 3 of ANSI B30.2 1976 " Overhead and Gantry Cranes."

5 H.

Spent fuel, safe shutdown equipment, and decay heat removal equipment are separated and evaluated to ensure

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that potential load drops from OHLHS will not jeopardize the safety of the plant.

Sufficient redundancy has been designed into safety-related systems to ensure that potential load drops will not preclude safe shutdown or decay heat removal.

A review of OHLHS was performed in accordance with NUREG-0612 and following the guidelines of enclosure 3 to the Nuclear Regulatory Commission generic letter dated. December 22, 1980, as amended on February 3, 1981.

The OHLHS in the following buildings were reviewed:

e Auxiliary building.

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Fuel handling building.

e e

Containment building.

e Control building.

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e Diesel generator building, e

Auxiliary feedwater pumphouse.

e Nuclear service coolin water pumphouse.

e ALTERNATE RADWASTE BUILDING

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The tu dw a nsfer, and solidification buildings do not house spent fuel, safe shutdown equipment, or 15 decay heat removal equipment and therefore were not reviewed.

9.1.5-17 Amend. 15 3/85

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O TABLE 9.1.5-2 (SHEET 7 OF 8)

Sa fe ty-Basis Safety-Related for l}$

Load Maximum Related item on Con-Ho i st/ Crane Design Weight Vertical item in Lower fo rmance/

Refe rence g

Eauionent Capacity iib)

Sta nda rd fib 1 Lift Ifti Load Path Elevation Exclusion Drawine s remarks Control Building - Level 3 ESF chilled 4,000 7

3,500 8

Yes Yes 4

Fig. 9.1.5-5 water chillers (sheets 26 and 27)

Control Building - Level 4 Normal chilled 8,000 3

7,000 8

No Yes 4

Fig. 9.1.5-5 watsr chillers (sheet 25)

Normal chilled 8,000 3

6,900 8

No Yes 4

Fig. 9.1.5-5

' water pumps (sheet 25)

AHe r ea-te Radwesie B v:td;,,0

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5 s o, oo o 35 ho Yes 2.

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k VEGP-FSAR-9 9.3.3 EQUIPMENT AND FLOOR DRAINAGE SYSTEMS

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The equipment and floor drainage systems collect effluent from A

equipment and floors, separate the effluents according to their activities, and transfer them to the proper area for processing or disposal.

The systems consist of collection piping, equipment drains, floor drains, vents, traps, cleanouts, oil separators, sampling connections, and collection sumps.

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9.3.3.1 Design Bases j

9.3.3.1.1 Safety Design Bases A.

The drainage systems are designed so that they do not compromise the negative pressure boundary.

The areas that are maintained under a negative pressure are discussed in section 9.4.

B.

The drain systers from engineered safety features (ESF) equipment rooms are designed to prevent flooding f

of ESF equipment via backflow through drainage piping.

2 C.

The control building drain system, the fuel handling building and electrical chase tunnel drain system, the auxiliary building flood retaining room drain system, the auxiliary building and miscellaneous drain system (except for the nuclear service cooling water (NSCW) ge e testfI chemical control building drain pipin and the containment and auxiliary building dr in system (except for the drain piping inside the containment building) are designed to Seismic Category 1 requirements.

The isolation valves that isolate ESF equipment rooms and negative pressure areas are procur,ed as Nuclear Safety Class 3 but installed as l

Nuclear Safety Class 4.

t D.

The design allows for detection of leakage from ESF systems.

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l 9.3.3.1.2 Power Generation Design Bases A.

The design and arrangement of the nonradioactive j

drainage systems allow diversion of potentially radioactive contaminated materials to the liquid waste processing system.

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B.

The liquid radwaste collection system collects

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potentially radioactive liquid wastes, at atmospheric

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pressure, from equipment and floor drainage of the containment, control building, auxiliary building, d;""",A,-

fuel handling building, radwaste transfer building, O

%gs/c coi/$erp and radwaste solidification building.

All such d drainage is conveyed by gravity to sumps or tanks within the respective buildings and pumped from there to the waste receiver tanks.

Chemical wastes collected from laboratory equipment decontamination areas and radiochemistry laboratory sinks drain to the chemical drain tank.

Potentially radioactive wastes

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from the laundry, from the automatic utensil washer in J

the radiochemistry laboratory, and from personnel decontamination shower facilities are collected in the laundry and hot shower tank.

C.

The turbine building drain system collects the normally nonradioactive floor drains, equipment drains, sampling wastes, and other miscellaneous drains.

The fluid from such drains is usually sent to

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the oil separator prior to discharge to the environment.

If the fluid becomes radioactive, it is treated before disposal as discussed in paragraph 9.3.3.2.3.9.C.

l3 D.

Systems which are not potentially radioactive are provided for the collection and disposal of storm drainage, oily waste, chemical waste, and clear water waste.

4 E.

Sump pumps are designed to discharge at a flowrate adequate for preventing sump overflow during normally anticipated drainage periods.

Generally, sump capacities provide a live storage capacity consistent with an operating period of not less than 5 min with one pump operating.

F.

Floor drains are collected in a closed floor drain tank provided with a vent connection to the exhaust

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system.

G.

Non-safety related.outside area drains are Seismic Category 2, unless otherwise noted (figure 9.3.3-3, 20 sheet 10).

9.3.3.1.3 Codes and Standards Codes and standards applicable to the equipment and floor drainage systems are listed in table 3.2.2-1.

Amend. 3 1/84 9.3.3-2 Amend. 20 12/85

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VEGP-FSAR-9 holdup before pumping to the auxiliary building for oil and radioactive material removal.

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9.3.3.2.3 System operation The various subsystems drain directly to the appropriate collection point by gravity.

Sump pumps are started automatically when a predetermined high level in the sump is

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reached.

The subsystems and their operation are described in subsequent paragraphs according to their classification as nonradioactive or potentially radioactive.

There are two sump pumps for each sump except for the NSCW pumphouse sumps, electrical tunnel sumps, diesel generator l22 building sumps, electric steam boiler building rump pump, auxiliary feedwater system shmps and electric rsnam boiler Pa @ "'"3p l19

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byilding sump,es4 3 porfable sum,p ppP 9

is V sers i waier [,ow Tk alternode. rad tocrd e Ausldig aump

• anolio~i 6 The sump pumps are controlled Uy a main level control and a backup level control per sump.

When the sump level rises to a preset level, the pump is started by the displacement action of f

the level switch.

If the level continues to rise, a second-(

level switch starts the second pump.

Sumps that are equipped with only one sump pump are provided with one level control.

19 Failure of one pump to start will not prevent the second pump from starting.

If the level continues to rise, a separate high-high level switch is incorporated in the design to activate an annunciator in the control room advising the operators that a flooding condition is imminent.

After the pumps lower the level to a point just above the pump suction, a

third displacer on the control level switch stops both pumps.

9.3.3.2.3.1 Potentially Radioactive Drainage.

Fluids conveyed I

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by potentially radioactive drainage systems flow by gravity to sumps in the respective buildings and are then pumped to the waste holdup tanks (figure 9.3.3-2).

9.3.3.2.3.2 Storm Drainage.

The storm drainage system

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collects water resulting from precipitation on all building i

roofs and areaways and paved and unpaved surfaces outside the

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buildings and conveys it to a natural body of water.

i 9.3,3.2.3.3 oily Waste.

The oily waste system collects l'iquid

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waste which enters floor drains located in areas which are i

normally not sources of potentially radioactive waste, and l

Amend. 19 9/85 9.3.3-5 Amend. 22 2/86 l

- - - - - J

VEGP-FSAR-9 sump would contain no oil and is pumped out periodically to the waste water retention basin.

P.

Lube Oil and Fuel Oil Storage Area Sump A diked area is provided for the clean lube oil tank,

)

the dirty lube oil tank, and the fuel oil storage tank.

The truck station is curbed and surfaced; discharge from this area is drained to the dike for the oil storage area.

The dike design provides capacity for single complete drainage from the largest tank plus the rainwater associated with a 100-year

)

rainfall (11 in. in 24 h).

The diked areas drain to a sump with a single pump.

Discharge from this area is routed to the turbine building drain system oily waste separator.

Q.

Water Treatment Building Sump This sump collects drainage from the water treatment building drains.

The sump has two sump pumps which discharge to the waste water retention basin.

R.

Electric Steam Boiler Building Sump This is another normally nonradioactive drain I

collection point.

INSER T Gh 9.3.3.2.3.10- fotentially_ Radioactive Drain Collection Points.

A.

CCW Drain Tank This 15,000-gal tank is located in the auxiliary building.

It collects the normal and potentially radioactive drainage containing chromates from the equipment and floor drains associated with the CCW and ACCW systems.

A single pump discharges to the CCW and ACCW. surge tanks.

If the CCW becomes radioactively

• )

contaminated, it will be treated prior to offsite

/

disposal.

A flange connection is provided for this 19 purpose.

B.

Containment Sumps and Reactor Cavity Sump These sumps are located inside the containment and I

collect normal and potentially radioactive equipment and floor drainage from inside the containment.

The pumps normally discharge to the floor drain tank.

The discharge line is equipped with pneumatically operated

)

Amend. 3 1/84 9.3.3-10 Amend. 19 9/85 C

INSERT h

SECTiotJ 93.3.2.3.9 S.

ALTERNATE _ RADWASTE _. BUILDiblG FLOOR SUMP THIS SUMP. lS _ LOCA TED IM THE. ALTERNATE RADY.'ASTE BUILolNG.

i.._

. AND ccLLECTS FLOOR ORAINAGE FROM THE ALTERNATE]QWASTE.

I

. _. _... __.i_..

BVIL0 LNG.

A PORTA 6LE. PUMP.

IS LITILIZED. TO P0HP L___

._l______

__ _ [._...

I

._QUT_ THE SUMP. ccNTENTS. -

PIPING lS PP0tl.IoED. 50 THAT.

. _..._. d._.

f

-l q__.__

.THE SUHP. OlscHARGE. MAY BE DIRECTED.__TO THE. AUKILIARY l

TOTHEY BUIL9lN$ FLOOR ORAIN TANK,

OR IF CCMTAHINATED >

_ AUXILIARY BUILDING LVASTE HOLDUP TAHK.

A SEPARA TE t.EAK. DETECTING _ FLOOR DRAlW 1./NE,

W/7H. A LOCAL. Y

___3 AUOl8LE ALARM

/S PROVIDED f~cR THE AREA INS /02 i.

THE DEMINERAL/EER. VAULT.

A NORMALL/ CLOSED VAL.VE.

7..

-. _...--_ [ ALLOWS CM7 ROLLED. DRAIWAGE FROM THIS. L/NE. TO THE -.

i i

! Bil/LDING SUIP.L.

t I

I i

7-.

.ap..

9 q

e..

h_

.y

)

LAO-Ot t e F/79

VEGP-FSAR-9 9.3.3.4 Tests and Inspections h

A.

Testing During Construction d

(

Equipment and floor drain lines in the auxiliary,/ind

/

control, fuel handling, radwaste solidification, radwaste transfer buildings and radwaste transfe<

tunnel are hydrostatically tested with the static leak 5 19 test method by filling the lines with water under atmospheric pressure.

Pump suction and discharge

(_

piping are hydrostatically tested at 1 1/2 times the design pressure.

Where these tests are not practical, the exposed welds that are not hydrostatically tested are nondestructively examined.

B.

Operational Testing Capability The operability of equipment and floor drainage systems dependent on gravity flew can be checked by normal usage.

Portions of these systems dependent upon pumps to raise liquid waste to gravity drains niay be checked through instrumentation and alarm registry in the control room.

I n.s trum9t tat ic.n.. Applications 9.3.3.5 t

Aa described in the safety evaluation, a high-level indication light is provided in the control room with a common high-level alarm for each ESF equipment room.

Level indication, in addition tc the level operated switch used for pump cor.t><1, i r.

provided for sumps in the containment to provice backup indication of the presence of large leaks and to provide information as to the source.

(

Amend. 5 4/84 9.3.3-13 Amend. 19 9/85 l

P

....w.-.._

a VEGP-ESAR 5 TABLE 9.3.3-2 (SHEET 1 0F 2)

SUMP PARAMETERS l

Project <a:

Classifi-Top cation Elevation (Entering of Sump Dimensions (ft)

Sump Lines)

(ft) (in.)

Long x Wide x Deep Normally Nonradioactive:

Auxiliary building 414 119 3

5.0 x 8.0 x 6.0 Clean water 414 119 3

4.0 x 6.5 x 6.0

~

Main steam and feedwater N/A 198 0

5.0 x 8.0 x 6.0 tunnel Turbine building 424 195 0

6.5 x 8.0 x 15.0 1

Control building 414 160 0

4.0 x 6.5 x 14.75tb>

NSCW pumphouse 414 205 0

2.5 x 5.0 x 5.5 Diesel generator N/A 175 0

2.5 x 5.0 x 5.5 electric tunnel Diesel generator 414 220 0

2.5 x 5.0 x 5.5 building oily waste Penetration room d' 414tc' 119 3

4.0 x 6.5 x 4.0 i

Auxiliary feedwater 414 215 0

12.0 x 12.0 x 10.0 Radwaste solidification 424 192 0

12.0 x 6.0 x 15.0 building equipment drain Radwaste solidification 424 192 0

12.0 x 6.0 x 15.0 l

building floor drain

--+

Auxiliary boiler room 424 219 6

5.5 x 5.5 x 6.0 North firewater pumphouse 626 208 0

32.0 x 6.0 x 6.0 oily waste separator Water treatment building 626 220 0

.5.5 x 11.0 x 8.0 Lube oil storage area 424 219 0

34.0 x 12.0 x 3.0 MTERNATE FADWASTE BUIL0 LNG 4%4 32 0 G

4.0 X 4 0 # 40 FLCCR DRAlH i

.t

VEGP-ESAR-9 9.3.4.2.2

System Description

The BRS is shown in figure 9.3.4-2.

The codes and standards to

(

which the individual components of the BRS are designed are

(

listed in section 3.2.

When water is directed to the BRS, the flow passes first through the recycle evaporator feed demineralizers and filters and then into the recycle holdup tanks.

The recycle evaporator feed pumps can be used to transfer liquid from one recycle holdup tank to the other if g

desired.

When sufficient water is accumulated to warrant

(

evaporator operation, the recycle evaporator feed pumps take suction from the selected recycle holdup tank.

The. fluid is pumped through the recycle evaporator, where dissolved gases, i.e.,

hydrogen, fission gases, and other gases, are removed in the stripping column before the liquid enters the evaporator i

shell.

These gases are directed to the gaseous waste processing system.

During evaporator operation, distillate from the evaporator

^ i flows continuously to the RMWST.

Also located in this flow path are the recycle evaporator condensate demineralizer and the recycle evaporator condensate filter.

A radiation monitor continuously monitors the evaporator distillate; on detection

(

of high activity, a three-way diversion valve is tripped to return the distillate to the feed demineralizers and to the recycle holdup tanks.

The evaporator concentrates the boric acid solution until a 4 weight percent solution is obtained.

The accumulated batch is normally transferred to the boric acid tanks in the CVCS through the recycle evaporator concentrates filter.

Before

' transferring the boric acid from the evapor~ator to the boric acid tanks, it is analyzed; if it does not meet the required chemical standards, it can be diverted back to the recycle o

holdup tanks for reprocessing or to the liquid waste processing system for disposal.

~

Connections are provided so that, if necessary, the recycle evaporator can be used as a waste evaporator (and vice versa).

All portions of the BRS which contain concentrated boric acid are maintained at a temperature of 265*F or higher.

9.3.4.2.2.1 Component Descriptions.

A summary of principal component data is given in table 9.3.4-3; the code requirements are given in section 3.2.

IW ADOITION, PIPsMG CONNECTIONS HAVE BEEN PROVIDED TO PERMIT THE

(

USE OF A MRTABLE DEMINGMALIEER $YSTEM LOCATE D IN THE ALTERNATE RADWASTE BUllOlNG*

^

~

^

~

9.3.4-41

.f

VEGP-FSAR-9

,un el wi l l be concentrated to no more than 4 weight percent rather than to 12 weight percent, as is permitted for the waste evaporator.

After the recycle evaporator is used to process water from the liquid waste processing system, it is thoroughly rinsed.

During initial recycle processing, the condensate is directed to the waste condensate tank for analysis before it is recycled to the RMWST.

Depending upon the purity of the evaporator bottoms, the concentrated boric acid can be recycled to the

(-

boric acid tanks, returned to the recycle holdup tanks for reprocessing, or transferred to the liquid waste processing system for disposal.

9.3.4.2.3 Safety Evaluation

~

Malfunctions in the BRS do not affect the safety of station operations.

The BRS is designed to tolerate equipment faults with critical functions being met by the use of two pieces of equipment so that the failure of one will, at most, reduce the capacity of the BRS but not completely shut it down.

Because of the large surge capacity of the BRS, the occasional

(

nonavailability of the recycle evaporator can be tolerated for brief periods of time.

Also, backun_is croy,ided, the waste r

evaporatorx[AND A IURTABLE *DFJf/NERALIZER s>5 TEM LOG 4TED IM 7//E TE RADWASTE BU/lD/At6, 9.3.4.2.4 Tests and Inspections The BRS is in intermittent use throughout normal reactor operation.

Periodic visual inspection and preventive maintenance are conducted using accepted industry practice.

Refer to chapter 14 for further information.

9.3.4.2.5 Instrumentation Application

(

t The instrumentation available for the BRS is discussed below.

Alarms are provided as noted.

There is also a common alarm on the main control board which indicates any alarms on the BRS panel.

9.3.4.2.5.1 Temperature.

Instrumentation is provided to measure the temperature of the inlet flow to the recycle evaporator feed demineralizers and to control a three-way bypass valve.

If the inlet temperature becomes too high, the i

instrumentation aligns the valve to bypass the demineralizers.

(

Local temperature indication and a high-temperature alarm on the BRS panel are provided by this instrumentation.

9.3.4-47 r

=w" e

rmm mm

VEGP-FSAR-9 mechanisms to allow chiller operation down to approximately 10 percent of its capacity.

9.4.3.3.2.3.7 Radwaste Solidification Building Elevator Machine Room.

The elevator machine room is served by an

)'

outside air supply system that provides fresh air, heated as required, to the elevator shaft under positive pressure.

The elevator machine room is supplied with outside air from an intake plenum at el 263 ft 6 in.; air is exhausted to the atmosphere at el 263 ft 6 in.

This system assists in oinimizing exfiltration from the radwaste solidification

}

building.

9.4.3.3.2.3.8 Health Physics Building.

The 100-percent outside air supply is filtered and conditioned by the air supply unit and is distributed to the health physics building.

Supply air conditioned to 55*F is delivered to the different zones.

Each zone is equipped with an electric reheat coil controlled by a. space thermostat.

A package electric steam humidifier located at the main supply duct is initiated when the space relative humidity becomes lower than the preset value of the space humidistat.

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

/NSEfT (j) r 9.4.3.3.3 Safety Evaluation Since there is no safety design basis for the radwaste solidification building and radwaste transfer building ventilation systems, no safety evaluation is required.

9.4.3.3.4 Tests and Inspections I

The radwaste solidification building and radwaste transfer building ventilation systems are designed to permit periodic inspection of system components to ensure the integrity and capability of the system.

5 j

The fans are performance tested by the manufacturer in accord-h ance with AMCA Standard 210.'2'

_J s

HEPA filter elements are tested individually prio,r to installa-tion to verify an efficiency of 99.97 percent with a thermally generated, monodispersed, 0.3-um DOP aerosol.

HEPA filter banks are tested in place prior to operation and periodically g

I' 9.4.3-18 i

L

~.

- i l

INSER T 9.4.3.3.2.3 9 AlTERNA TE. RADWASTE B U/L D /N G,

. Coxnwuous_ MANUAL R/DGE VENTILA TORS -

AT PADV/DED FoK -

THE ALTERNATE RADWASTE. BU/LD/MG.

A VENT l./NE CDNNECT/0Al

/3-PROV/DEO.

70 INTERFACE-- W/7//'

INE VENOGR -40PPL/EL) -- --.

\\

THE POTENTIALLy.

CDNTA/NER._ VENT 3FJTEM -. To EXHAUST.

7 --- __ - ---

l'dATAM/NATED.-- fR&ESS A/R-. TUROUGH-. 7WE h/A/L/ arf B///LD/AG-

~ ;

I

. FILTRA TIOM-SXSTEM. --

PAVVM/DNS.

ARE /At2t/DED '

70 EXHAUSE

~

-- - - /1/2 FROM THE 240WASM.7&NA/E/-

AREA AAfD-. PlkE T/O N S o/= -.

. THE R4DWASTE TRANSFER - BullD/A/q THRet/GN.THE NX/UAh Au/LD/NG. f/L TRA T/DN-. sy3 TEM PR/OR To WPL ET/0Al. df -.

_ - THE - AADWASTE JOL/0!F/CA T/oM 8t//LD/A/C

• 7

--,eM-_-

w.

-eni...

e

-.e

-.#-.9-+

---9 s - - - -

T a

P l

7__

I

- + -

l l

- - ~

~

\\

~.

9.A l.I3I

. F/RE AREA 1 - ARB -LL - 1 f:<< pr ofn fio n (TO BE. PROV/DED w:+h n

.-.f 6 A 0 (h9ng C b

- ~

j i

l

___ _ __4._.

a

=

u_ _ _ _ _ _ _.

i 1

. -. ~

-m

-m

+

w__-.

-r--

.m

~ - _ - -

.-_-e.-

e.,.

n I

l l

l I

L.-

l l

i i_ -

1 l

W

.-_w__

~

--w LAO *0SIO 7/75

VEGP-FSAR-11 Portions of the LWPS may become unavailable as a result of the malfunctions listed in paragraphs 11.2.1.1.1 through 11.2.1.1.3.

Ample surge capacity of the system and the low load factor of the processing equipment permit the system to accommodate waste until failures can be repaired and normal plant operation resumed.

In addition, the LWPS is designed to accommodate the anticipated operational occurrences described in paragraphs 1.2.1.1.4 through 11.2.1.1 As us itione meast.ME ASSURANCE TWAT Lied /D WASTES CAW BE PROCESSED DtJRIMG ALL PLANT CONDIT0ds PIPIMi coNNfcT10NS HAVE BEEM INSTALLED IN TWE LWPS PROCESS, STREAM 1

.1.

.1 Pump a

ute TO ALLOW USE OF A PQRTABLE PEHINERAllEER.sysTE M ATED IN TMC ALTERMA,T DWASTE 80/LDING.

n surge capacity is Where operation is not essent al available, a single pump is provided.

Two reactor coolant drain tank (RCDT) pumps are provided because the relative inac-cessibility of the containment during plant operation would hinder maintenance.

Pump repair and replacement is facilitated by using three standard pump designs for the eight applications in the LWPS.

To protect the pumps from damage due to loss of T~

suction, each pump is interlocked to stop on a low level con-dition in the tank feeding the pump.

11.2.1.1.2 Eilter, Strainer, or Demineralizer Plugging j

Instrumentation is provided to give local indication of the pressure drop across all filters, strainers, and deminera-lizers.

Periodic checks of the pressure drops, provide indica-tion of the equipment fouling, thus permitting corrective act-ion to be taken before an excessive pressure drop is reached.

11.2.1.1.3 Waste Evaporator Failure The waste holdup tank and sometimes the floor drain tank pro-vide feed to the waste evaporator.

Each tank has sufficient surge capacity to accommodate more than 2 days of normal inflow

^

without evaporator processing.

This is based on an initial tank level of 30 percent and inflow according to table 11.2.1-1.

If the waste evaporator for one unit is out of service, l

interconnections allow the waste evaporator for.the other unit

~

to be used in place of the nonoperative evaporator.

Intercon-nections also permit the recycle evaporator in the boron recycle system to_be u e evwar i f ev-neceaaaty. IN Acourlost, pipaus CONNECTIONS HAVE BEEW PROVIDED TO AERN/7" TAfE f

usE OF A CRTABLE DEMINERALIEER SYSTEM LOCA TED IN THE 41TERAfATE R40 WASTE BUILDIMG.

k P

T 2.1-2

Zn ADDITICN, Art ALTERNATE RAowAsTE BUILDING /S P90VfDED 70 MLOW t/SE ef PCRTABLE RADWASTE SYSTOLS (

DENINERAL/ZERS, DEMTERlWG/ORTING, S0t./p/f/C7 CUPPLIED BY CCNTRACTORS 108 HANDLING S0UD W4STEs FROM PLANT OPEAATioN.5 DURING ALL PLANT CCHOff/ CMS (SEM SECTICN //,4 ft,4)

VEGP-FSAR-1 C

'x

/N 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 Departmant of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regulations, including 49 Code of Federal Regulations (CER) 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 section 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 p IN THE system components and piping are provided in section 3.2.

f RAPWASTE rovisions are madeAto utilize a mobile radwaste so'lidification sot DFrAnd ystem in the unlikely event that the inplant system becomes SullDING unavailable for a prolonged period of time.2 The solid waste management system design., parameters are based

},

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

The solid waste management system airborne process effluents are released through the radwaste building vent and are discussed as part of the 10 CFR 50, Appendix 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 GDC 60 of 10 CFR 50, Appendix A, and Regulatory

)

l 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) remote system operation, remotely actuated flushing, and shielding of components containing radioactive materials.

Additionally, l

access to the process equipment and solid waste storage areas

.)

i is controlled to minimize personnel exposure by suitable

(

barriers such as locked doors or gates or control cards.

(See l

paragraph 12.3.1.2 and section 12.5.)

The solid waste management system has been designed to conform with the design 5

~

l criteria of NRC Branch Technical Position ETSB 11-3.

.)

11.4.1-2 Amend. 5 4/84 i

i VEGP-FSAR-11 1

-y J

within the operating specifications provided by the vendors.

I High acid resins may require some time in a basic environment.

11.4.2.3.12.2 Concentration and Type of Radwaste.

The

~])

identity of solids, dissolved solids, and their concentrations transferred to the solid radwaste system is ascertained and controlled by the solid waste management system equipment and its operation.

In the case of slurries, the decanting tank is used to control concentration prior to. drumming.

11.4.2.3.13 Flush Water Disposition For those components in the radwaste solidification building, flush water is directed to the radwaste solidification building equipment drain system.

When this drain tank is full or the activity level reaches a predetermined setpoint, the tank contents are pumped to the auxiliary building waste holdup tank for evaporative processing.

For those components in the transfer building, flush water is directed to the auxiliary building waste holdup tank.

All lines in the transfer tunnel have provisions to be flushed to either the solidification building equipment drain system, the auxiliary building waste holdup tank, or tanks whose contents are suitably processed.

i I l d ' '9 '4 See l ri s e r [ [

. %g x.-

,- m

')

-~.

~n

.)

11.4.2-24

.. I

5nSel'f $

//. 4.2 4 JCL/0/F/ CAT /0W PACGRAH AlTERNATILES Two s/ STEMS HAVE BEEN. CONS /DERED

/~0R HANDL /NG SQL/p WASTES FRCH. PLAN 7*

ofERAT/6NS.

-. - - _. & THEL' DES /GNED.__ SOL /D _ WASTE _ HANAGEMENT GY37Ekl. AS DESCR/8ED

_ _/N JECTIONi- //. 4. 2. I end i1. 4 2. w L.

.--9.--...-_.

_-. bJ PORTABLE _._ RADWASTE SyJTEMS_. SHPPL /ED _. 87...

VENMR S,,-

t EVALUATIONS OFNTHESE. AL TERNA T/VE.Sl - COVER /NG__ N//RRE

-l

-._ lREGULA TIONS..oM SM/PP/NG AND 8//R/AL CA/TER/A, - 4D/A T/0 } _----.

_. EKPOSURES-To _.CPERAT/MG AND NA/NTENANCE

/ERSONNEl

/MVE. --

- _--- BEEN PERFORMED. _.-

// A. ? 4. /.. DES /GNED

$dL/D. }VASTE MAN 4GEMEN7~. SXSTEM.

bu3 TD

. CDHVIERC.%I AND-. SCHEDULE _.

CDNCERNS

/DENTIF/ED -.

W/7?/

RE3pECT $ TO--

THE-DES /GNED- <SQL/D WASTE MANAGEMENT -.-.

r i

+ _ - -

iS/37EM.b_. 7HE $ AADWASTE-. SOL /D/F/ CATION 8t//LD/A/4 4ND PORT /MS-i i

LOf T//E !_R40WA57E 7RANSFER-;Bu/LD/NG_ AND TXANSFEAL TuAMEL-b__ _ _ -.

w/LL. NOT-bel. AVA//. ABLE PR/0R__ TO

/NITIAL_ PLANT JTARTt/P. --

..I_ m p_ _ _.

s,

.s

... 7/fEREMRE, ASYSTEA}S_ LOCA TEC. IM THE.SE L 8t//LDINGS._ M/t.L N 07 BE_

. - _ - -. - - - p _ -_

-. - ~

-w_---

USED AT_7HIS ;T/ME, L -.

LAO-OS S O 7/75 l

[

e e.

~

// 4-2 d

/ / 4.

7. 4 -

2-70RTABLE RADh&43TE SYSTE/4 VEGP wtLL uTIL/EE VENDOR JuPPL/ED PORTABL E RADWASTE EQU//%1ENT TO _ PROV/DE FOR D/SPOSAL Of SPENT. REJ/Ns, RALYOACTIVE

' CARTRIDGE FILTERS,

EVAPORATOR CCNCENTRA TESy. BACKFLWHABLE F/LER l CRUD, LAND CHEMICAL WASTES VIA. DEWATER/HG-- OR-t

-. JOL/D/f/ CATION..--

.IN ADDITICAl, A.MRTABLE DEMINERAL/EER J

r

' SY3 TEM _IS AVAlLABLE__5AS. AAf ALTERNA TE.

MEANS__OF_._ l'ROMSSIAlq_.I

. THE CulTENTS i 0F. T//E WASTE HOLDUP TANK,. C//E' N/ CAL. DRA/M--

TANK _' floor drais +enK - -

AANO. 80R0N. RECYCLE _ J h'OLDUP TANK.

THESE _ J}0TEMS -

ARE Not/ SED

/N_ THE-ALTERWATE RADIVASTE-BU/LD/MG - (AR8 -) -

4 WH/W /S. LOCATED-- ON.77/EI. JOUT/C J/DE_ OF THE-RADWASTE_

_ TRANSFER BUILD /NQ_

AS J//Ott/N IN EGuRE

l. R. 5L~)3.

VA VESY_ AM -.PROV/DED. 70 ALLOW PROCESS /NG CF Y ISOLATIO i

.IVASTE$STREAbts ---.E/THER-W/71L EX/ST/NG SY3TEMS OR AT..

_. the-_ ARB.- _71/E VALVE 3_.. ARE HANUALL)'

CPERATED - TO t

- - l_ AeHIEVE - THE. DES / RED-CONF /GURA TION..

DEL /b'ER)' Of ----.-...

._1-

. WASTE STREAMS TO THE_ AR8

/3 CONTROLLED FROM-

. LOCAL _ PANELS.. NEAR THE-WASTE STREAM SOURCE.

LAO-OS 3 0 7/75 e

//, tA ? tf FLANGED CONNECT /0NS ARE PROV/DED AT THE ARB TD INTERFACE

WITH THE VENDOR duPPLIED SYSTEMS -

MAJOR COMFONENT.S FOR

. PORTABLE-RADWASTE _ S)37Eb/S_

TYP/CALLy

/NCLUDE :

FA'0 CESS

.. y -

LINERS, fROCESS. SK/Ds ANO. CONTROL PANEL. S.-

I. RADIOACTIVE. CONDENSATE __AL/JHING _ DEAF /NERAL/EER_' RES/NS.,

(

i i._BACKELUSHABLE BLTER CRUD., _ AND. APENLRES/N3 JRdhy l

j THE... L /GUID WASTE PROCESS /MG. 3)GTEH AND _ THE.2 TEA &fL i

GENERAT6R BLOWDoiVM sXSTEM WILL BE DEWATERED.

THE DEWATERING SYJTEM SUPPL /ED B7 VE NDdR AlLDW3 THE l

WATER 70 BE REMOVED FROM THE JPEA'T RES/NS

/Af THE SHIFP/NG. cDNTA/NERS-A VENDOR JoPPL/ED coNTA/NEAL -.

. _. VENT /d PROV/DED R?R' THE SH/Pf/MG CONTA/NERS, THEREBY, i

M/M/M/EING _._ LEAKAGE INTO THE-.. 8WLD/NQ..__

A VENT L/AE.

p _ __ _ u_ _ _... _ _

. TO A... MONITORED HVAC. EXHAUST DUCT IN. THE_. A ux/L/A RY

-_ BUILOING-.I$ PRQVIDED-TO. INTERFACE.

W/7H THE_ 1/ENDOAL__ -

.. _. SYSTEM..

1N ADDITION.,

DEM/NERAL/ZEK RES/NS FROM THE-s

._ PORTABLE.. DEM/MERAL/EERS [ D/Scus5EO- /Af. //. 2 )

CAN 82

.. _. SLu/CED.

0. THE CDNTA/NER F/LL S/(/D FOR DELLHTER/WCy L Ao-os t o 7/7s

' # 2 c' AND DISPOSAL.

7

. An. MRC approved 7hxess 0nTROL PRocrRAV1 ( PCP) tviL L.

' BE_ REQUIRED-.0F_ THE- &'ENDOR..AND... APPROPR/A TEly-REFERENCED i

/N_ THE I VEGR__ PCPNPR/OR_ TO _ ANY. ACTUAL-OPERA TION. --

_._. d..____ -....

L._.

i

_ _4 n

l I,F 77/EI _ BUR /AL-S/TE DOES FOT ACCEPT _. DEWATERED RES/NS f

j i

I

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VEG, P

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VEGP-FSAR-12 k

12.2 RADIATION SOURCES This section discusses and identifies the sources of radiation

(

that form the basis for shield design calculations and tha sources of airborne radioactivity used for the design of per-sonnel protection measures and dose assessment.

12.2.1 CONTAINED SOURCES The shielding design source terms are based upon the three plant conditions of normal full-power operation, shutdown, and design basis accident events.

12.2.1.1 Sources for Full-Power Operation The primary sources of radioactivity during normal full-power operation are direct core radiation, coolant activation processes, leakage of fission products from pinhole defects in fuel rod cladding, and activation of reactor coolant corrosion products.

The design basis for the shielding source terms for fission products in this section is cladding defects in fuel

[

rods producing 1 percent of the core thermal power.

The design basis for activation and corrosion product activities is derived from measurements at operating ants and is indepen-dent of fuel defect level.

-w.

rusger 12.2.1.1.1 Reactor Core

-The primary radiation from the reactor core during normal oper-

~

ation is neutrons and gamma rays.

Figures 12.2.1-1 and 12.2.1-2 show neutron and gamma multigroup fluxes on the inside surface of the primary shield wall at the core centerline.

Gamma dose rate incident on the primary shield wall at the core midplane is shown in figure 12.2.1-3.

These figures are based

(

on nuclear parameters discussed in chapter 4.

Table 12.2.1-1 lists core gamma sources after shutdown for shielding require-ments during shutdown and inservice inspection.

12.2.1.1.2 Reactor Coolant System (RCS)

Sources of radiation in the RCS are fission product.s released from fuel and activation, and corrosion products that are circulated in the reactor coolant.

These sources and their base,s are discussed in section 11.1.

12.2.1-1

.I

INSER T (5) 1 77/E DES /GN BASIS FM SHIELOING SOURCE TERMS USED TO ESTABL/S// SH/ ELD /MG-PROV/J/0MS FDR THE ALTERNATE

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LAO-0510 7/ 75 4

VEGP-FSAR-14 1.

Construction acceptance testing is complete.

(-

2.

Component testing and instrument calibration are complete.

3.

Test instrumentation is available and calibrated.

,\\

4.

Support systems are available.

C.

Test Method 1.

Verify manual and automatic system controls.

2.

Verify alarms, indicating instruments, and status lights are functional.

3.

Verify design airflow.

4.

Demonstrate ability of fuel handling building exhaust system to maintain a negative pressure in the fuel handling building.

(

5.

Verify normal exhaust system isolation and post-accident exhaust system initiation on simulated high radiation signal from the exhaust ductwork radiation instrumentation.

10 D.

Acceptance Criterion The fuel handling building HVAC system operates as described in subsection 9.4.2.

14.2.8.1.37 Radwaste Building HVAC Preoperational Test (To BE PEWANED PR/dR 70 //LT/l/EM/0W C/* THE S)'378H)

A.

Objective To demonstrate operation of the radwaste building HVAC system.

B.

Prerequisites

(

The required portions of the following prerequisites are completed as necessary to support the 11 preoperational test:

1.

Construction acceptance testing is complete..

()

2.

Component testing and instrument calibration are complete.

Amend. 10 9/84 14.2.8-45 Amend. 11 11/84

(

VEGP-FSAR-14 14.2.8.1.51 Backflushable Filter System Preoperational Test A.

Objective l

l To demonstrate operation of the backflushable filter system.

B.

Prerequisites

(~l The required portions of the following prerequisites are completed as necessary to support the 11 preoperational test:

l l

1.

Construction acceptance testing is complete.

2.

Component testing and instrument calibration are complete.

3.

Test instrumentation is available and calibrated.

4.

Support systems are available.

l C.

Test Method 1.

Verify manual and automatic system controls.

2.

Verify system flowrates.

3.

Verify alarms, indicating instruments, and status

]

l lights are functional.

3 D.

Acceptance Criterion The backflushable-filter system operates as described i

l10 in section 11.4.

14.2.8.1.52 Radwaste S'olidification Systam Preoperational Test (70 BE FEAFCRHED PRIOR 7D ulRUZ4RCW Ac nVE 3)37EM)

A.

Objective To demonstrate operation of the radwaste solidification system.

i

'B.

Prerequisites

~~

l 4

l l

The required portions of the following prerequisites are. completed as necessary to support the 11

}

preoperational test:

g 6;

4

'a Amend. 10 9/84 f

14.2.8-59 Amend. 11 11/84 1,

s o

(

VEGP-FSAR-14 14.2.8.1.51 Backflushable Filter System Preoperational Test A.

Objective To demonstrate operation of the backflushable filter system.

B.

Prerequisites

()

The required portions of the following prerequisites are completed as necessary to support the 11 preoperational test:

1.

Construction acceptance testing is complete.

2.

Component testing and instrument calibration are complete.

3.

Test instrumentation is available and calibrated.

4.

Support systems are available.

C.

Test Method 1.

Verify manual and automatic system controls.

2.

Verify system flowrates.

3.

Verify alarms, indicating instruments, and status

' lights are functional.

l D.

Acceptance Criterion i

The backflushable filter system operates as described l10 in section 11.4.

14.2.8.1.52 Radwaste S'olidification System Preoperational Test nVE 3)37hM)

(70 BE FEAFORMO PR/0R 7D ul17dismV M A.

Objective To demonstrate operation of the radwaste solidification system.

~

'B.

Prerequisites

.The required portions of the following prerequisites are completed as nocessary to support the 11

)

preoperational test:

E i;

4

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Amend. 10 9/84 l

14.2.8-59 Amend. 11.11/84 1

,