ML20239A433

Proposed Confirmatory Radiological Survey Plan for Portions of Pathfinder Generating Station,Sioux Falls,Sd

ML20239A433
Person / Time
Site:	Lynchburg Research Center
Issue date:	06/04/1992
From:	OAK RIDGE ASSOCIATED UNIVERSITIES
To:	NRC
Shared Package
ML20239A138	List: IA-98-313, First Final Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a ML20239A137 ML20239A427 ML20239A433
References
CON-FIN-A-9076, FOIA-98-313 NUDOCS 9809090164
Download: ML20239A433 (24)

Text

PROPOSED CONFIRM ATORY RADIOLOGICAL SURVEY PLAN FOR PORTIONS OF Tile PATIIFINDER GENERATING STATION l SIOl'X FALLS, SOUTli DAKOTA INTRODUCTION Pathfinder Atomic Plant was a 66 MWe boiling water nuclear power station with a two region core, a boiler region and a superheater region. The boiler region of the reactor core utilized UO,, fuel enriched to 1.8% in U-235 and the superheater region utilized fuel ennched to 93%

in U-235. It was operated by Northern States Power Company (NSP) from 1964 through 1967 under operating license DPR-11. During this penod. low power testing and experiments were conducted. On September 16. 1967 the reactor was shutdown to repair a condensor tube leak.

Inspection of the reactor and associated equipment revealed that massive steam se;3arator failures had occurred and pieces of the steam separators were found throughout the primary system.

In 1968 the plant was converted to fossil fueled boilers and the nuclear portions were decommission.ed and placed in a safe storage con 6guration. The fossil plant at Pathfinder Generating Station is currently being utilized during penods of peak demand.

The residual radioactivity pencrated dunng operation of the nuc! car plant remained on site in storage under By-Product Matenal License 22-0S799-02. The dismanihng of the nuclear plant insched the isolation of the reactor building, fuel storage pool, and the lowcr levels of the fuel handling building from the rest of the plant; the removal of unused contaminated piping and equipment from the fossil plant arcas; and the decontammation of accessible areas and equipment which remt ned in the fossil plant arca The pnmary contaminants identi6ed were Co-60 Ni 63. FeA5 and Ni 54 on the pipmg and hardware 9 stems and Co-60. Cs 137. Cs-134. Eu-152. and Eu 154 in concrete-Prepared by the Environmental Nursey and site Assessment Program of Oak Ridge Instoute for Science and Education. Oak Ridge. TN. under interagency agreement (NRC Fm No A 407N between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy

! June 4.1992 gs 9809090164 980904 PDR FOIA 0'MEALI98-313 PDR

In luly 1989, NSP submitted a decommissioning plan to the Nuclear Regulatory Commission (NRC) for the nucwar portions of the site. Decommissiomng activities have been completed for the Fuel Handling Buildit,g, Fuel Transfer Vault, and the Reactor Building. The Fuel Handling Building and Fuel Transfer Vault are to be restored for non-nuclear use, and the Reactor Building is to be demolished.

Approximately 562 curies of radioactive waste material was removed from the buildings during decontamination and decommissioning activities and shipped off site. Contained within the fossil plant systems, is approximately 0.041 curie of by-product material, which is the result of deposits accumulated during operation of the nuclear plant.

The Nuclear Regulatory Commission Headquarters Office has requested that the Environmental Survey and Site Assessment Program (ESSAP) of Oak Ridge Institute for Science and Education (ORISE) perform a radiological con 0rmatory survey of the Fuel Handling Building, Fuel Transfer Vault, the Reactor. Building, and the Temporary 1.oading and Storage Building at the Path 0nder Generating Station m Sioux Falls. South Dakota.

SITE DESCRIPTION l Pathfinder Generating Station is located about 8.8 kilometers (5.5 miles) nonhcast of Sioux Falls, South Dakota on the Big Sioux River (Figure 1). The site indudes the Fuel Handling Building, Reactor Building, Water Treatment 'lant, Boiler Building. Turbmc Building, Administration Building, Security Office. Fire Pump House, Chlorine House. Control House.

Coohng Tower. Warehouse, and Rad Waste Sto. age The areas to be decommissioned include the Fuct Handhng Building. Fuct Transfer Vault, and the Reactor Building (Figure 2).

Additionally. the Tempc ary 1.o.iding and Storaye Budding used for decommissioning activities is to be surveyed The Fuel Handhng Building (HiBt is a ihrec .:ory t"::!d!"g. .. approximately 24 m x '*2 m The building includes the Operanny, Menamne. and Basement Floors (Figures 3 5). The l'HB contained the spent fuel pool and most of the hquid waste processing equipment

The Fuel Transfer Vault (FTV) contained the fuel transfer tube and connected the reactor shield

wl in the Reactor Building with the spent fact pool in the FHit (Figure 6L The Reactor Building (RB)is approximately 22 x 22 m and nses 26 m above the ground surface and extends 11 m below the ground surface (Figure 7). T;1c Reactor fluilding includes the Operating Floor, the Equipment Floor, the Plug Floor, and the Pump Floor. A separate compartment houses the sump and sump pumps, and is accessible from the Plug Floor. Figures 811 show the floor plan of the' Reactor Building.

The Temporary Loading and Storage Building (TLSil) is a 18 m x 21 m metal building on a poured concrete slab (Figure 12). It was crected for the decommissioning activities to provide a weather-protected equipment and waste container storage area, ITR14)SE i

j The purpose of the confirmatory survey is to provide independent document reviews and radiological data, for use by the NRC in evaluating the adequacy and accuracy of the licensce's radiological status report. relative to established guidelines RESPONSillil.lTY Work dewribed,in th s survey plan will be performed under the direction of Michele l2ndis, Pro.tect Manager and Betty Smith, Project 1.cader of the ESS AP of the Environment / Energy Systems Division of ORISE. The cognti2nt ESSAP site supenisor has the authority to make appropnate changes to the survey procedurcs as deemed necessary. Aftcr consultation with the NRC ute representative. the scope of the suncy plan may be altered Deviations to the survty plan or pnNedurcs will be documented it, the site log book.

l

! I i

i L

s PROCEDURES SURVEY ACTIVITIES A suncy team from ESS AP will visit the Pathfinder Generating Station and perform independent measurements and sampling in the Fuel Handling 11uilding, the Fuel Transfer Vault, the Reactor Building and the Temporary 1.oading and Storage Building. Survey activities will be conducted in accordance with the ORISE ESSAP Survey Procedures and Quality Assurance Manuals. The prxedures apphcable to the survey are hsted on pages 8 0 of this survey plan.

SURVEY PROCEDURES Exterior Surses l

Reference Grid Outdoor measurement and sampling locations will be referenced to prominent building features.

Esposure Rate Measurements l

Gamma esposure rates will be measured at I m above the surface at a minimum of 4 locations in the vicinity of the buildings using a pressurized ionization chamber (PICL Surface Scans Gamma surface wans will be conducted around the perimeters of the Fuel llandhng, Reactor.

i and Temporary leading and Storage iluildings and up to 10 m away from the btnidings at 12 m inter ah Gamma scintillation detectors and ratemeters with audible indicators will be used l ocations of cles ated direct radiation u dt be identified and marked for further investigation

.1

o

( ikta surface wans will be performed on the roofs, lower walls, and accessible upper walls using thir wmdow Ghl, and/or large area pas proportional detectors. All detectors will be coupled to ratemeter scalers with audible indicators. Particular attention will be given to cracks, joints, sents, and other locations where material may have accumulated.

Soll Sampling l

l Surface wil samples (015 cm) will be collected from a minimum of 4 locations around the penmeter of each building and from locations of clevated direct radiation identified by the surface wan',. Ikickground wil samples will be collected at a minimum of 4 locations off site.

Italedorjunu l l

I Heference Grid The 1 m gnd system utiliied by the licensee on the floors and lower walls will be utilized by I!SSAl' for referencing measurement and umpling locations. hicasurements and umpling locations on the upper walls and ceilings will bc referenced to floor grid coordmates or prominent b.uilding features l Espmure Rate S!casurements Itackground esposure rates will be determined for the building interiors at a minimum of 4 hrations of similar construction, but without a history of radioactive matenal use. lisposure rates will aim he measured within each roorn in the four buildings lisposure rate measurements will be perfor ned using a Plc Surface Scans Floors and lower walls will be scanned ming Natrill ramma scintillation, thin window Ght, and of large area gas proportional detectors All detectors will be coupled to ratemeter scalers s

with audible indicators. Panicular attention will be given to cracks and joints m the Door, 1 ledges, drains, ducts, and other locations w here material may have accumulated. Locations of clevated direct radiation will be identined and marked for further investigation.

Steasurements for Total and Removable Activity l

l Direct measurements for total beta activity will be performed on a minimum of 10% of the Door and lower wall surfaces; grid blocks will be selected using a random number rencrator. One direct measurement and one smear for removable contamination will be obtained from cach selected grid block. Direc measurements for total alpha activity will be performed at selected locations in each room.

Direct measurements for beta activity will be performed on the upper wall and ceihng surfaces

=

at a minimum of 1 measurement and : smear per 20 m , and at locations of clevated direct 2

radiation identiGed by the surfacc scant All detecton will be coupled to ratemeter scalcr5 with audible indicators Areas of residual contamination, in esceu of the guidelities. will be brought to the attention of the licensee site reprewntative.

Sliwetlaneous Sampling i

I e

Paint, water, Concrete, residue or other materials within the areas surveyed will be collected to determine if contamination is present.  !

6

I l-f I

SANIPl.E ANALYSIS AND DATA INTERPRETATION I I

Samples and data will be retumed to the CSS AP laboratory m Oak Ridge. TN for analyses and interpretation. Gamma measurements will be converted to units of pR/h (gamma exposure rate).

Direct measurements for surface activity will be reported m units of dpm/100 cm; Smears will I

be counted using a low background alpha / beta counter to determine gross activity. Soil, I l

concrete, paint, and miscellaneous samples will be analyzed by solid state gamma spectrometry.

The radionuclides of pnmary interest are cobalt 60 and cesium 137;. however, spectra will be reviewed for other identifiable photopeaks. A portion of the samples will be analyzed for strontmm 00 and analyted by alpha spectrometry for isotopic tiranium and plutonium. Data will be compared to the NRC guidelines established for release for unrestncted use. Results will be prouded in a draft report and provided to the NRC for review and comment. Data and samples collected as pan of this survey will be archived by ESS AP SITE CWil)El.lNI'.S Results of the sur%c) will be compared to the current NRC puidelines, l

For Co f() and Cs 13' surface contamination :hese guidchnes' are:

, , 5,(X10 dpm beta gamma'100 cm? (aserage over 1 m')

l-l 15,(XX) dpm beta gammall00 cm' (maximum in 100 cm')

l l 1.000 dpm beta gamma /100 city (removable)

The esposure rate guideline is 5 pR!h ahose background  ?

7 f

l

{

TENTATIVE SCllEDULE hicasurt ment and Sampling June 15 25,1992 Sample Analysis July 1992 Draft Suivey Report September 1992 LIST O F CURRENT PROCEDURES TO BE USED IN Tile SURVEY

/,pplicable proceducs from ORISE ESSAP Survey Procedures Manual (Revision 7; May 31,1990; include:

Section 5.0 Instrument Calibration and Operational Check-Out 5.1 General Information 5.2 Eactronic Calibration of Ratemeters 5.3 Ga nma Scintillation Detector Check Out and Cross Calibration 5.4 Alpha Scintillation Detector Calibration and Check Out 5.5 GM Octector Calibration and Check Out 5.6 Propo:tional Detector Calibration and Check Out 5.7 Pressurized lonir.ation Chamber Calibration and Check-Out 5.9 Floor Monitor Check Out 5.1: Victorcen GM Detector Check Out Section 60 Site Preparation 6.0 Reference Grid System (

l l

Section 7.0 Scanning and Measurement Techmques l 1

7.1 Surface Scanning l 7.3 Alpha Radiation Measurement  !

7.4 Ileta Radiation Measurement 7.5 Gamma Radiation (Exposurc Rate) Measurement 8

t i

Section 8.0 Sampling I'rocedures 8.1 Surface Soil Sampimg l

8.4 Water Sampling l

l 8.7 Determination of Removable Activity 8.8 Miscellaneous Sampling S.9 Sample Identification and Labeling Section 9.0 Integrated Survey Procedures 1

( 9.1 Background Measurements and Sampling 9.2 General Survey Approaches and Strategies Section 10.0 Health. Safety and Control of Cross-Contamination Section 11.0 Quality Assurance and Quality Control Appendix A Radiological Guidelines Appendix B Field Survey Forms 9

l

REFERENCES

1. " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for 13yproduct, Source, or Special Nuclear hiaterial " U.S. NRC, hiay 1987.

2. " Policy and Guideline Directive FC91 2, Standard Review Plan: Evaluating Decommissioning Plans for Licenses Under 10 CFR Partus 30, 40 and 70,* U.S.

Nuclear Regulatory Commission, August 1991.

I 10 j 1

i APPENDIX A -

l CONFIRSt ATORY SL'RVEY Pl.AN l COST ESTIS1 ATE

• PATilFINDER GENERATING STATION SIOUX FALLS, SOUTil DAKOTA Plan Preparation - 57,700 i Plan preparation includes the following activitics: document review, survey plans, trip planning. and the time and cost estimate.

On Site Activities . 582.tw On-site activities will include 56 man days at the site performing the following: mapping, exposure rate measurements, alpha, beta, and gamma surface scans. direct measurements and smears, miscellaneous sampling, and background measurements and sampling.

The on site expenses also include inp preparation (equipment calibration and packing),

unpacking equipment, and logging in samples.

Travel - 532,000 Travel includes travel to and from the site (airline and rental vehicles) hotel expenser and per diem.

Sample Analysis - 526.200 Based on the mformation obtained from ESS AP cost estimate sheets, smear analysis will cost approximately 59.000 and miscellaneous sample analysis will cost approximatch 517,2(X).

1 i1

---.___.-._._--.______,--,J

I I

j Report Preparation 5:4,800 l

l l

l The report preparation will include the following activities: tabulation of data, illustrations, writing and reviewing the draft and final reports, word processing, and reproduction.

f Total Cost Estimate - 5173,300 f

h i

• Estimates arefor suncy ofall areas listed in the NRC Rec]uestfor Technical Assistance received by ESSAP. Reduction or increase in the number of areas being suntyed would l result in changed to the original estimate in the 'On-Site Activities' and 'Sampic Analysis' categories. Due to the nature of the survey, the estimate is a best guess, site conditioru and sunty findings may change the scope of the sunry and increase or decrease the cost estimate. The NRC site representanve will be nonfied ifmajor changes to the scope of the sunty need to be taken.

1 l

12

Pr x1 PATHFINDER ,

I CENERATINO STATION 1

- _ + h

+ -s

, [f

?) ') C&NW i e o .x j *

'0 sB RANDON

\x g.-

,Y 5' fY Q f 2  % w' ~l

/ <

5 J '

 ? -]

1.. O (

m .

M l q]

S'QJx \

TALLS A  !

l /  !

t t -

t l

l-4 l

N 1 l i , .

I d,b, l

1 - - - -

niitnoe l

l b i

, ..co ntes j c  ;

i UtL[5 T!GURE

• Locat'on o' Pot h0nce - Ger.erating Station I .I

Frx2 f  :

i I

lv n I

l

! l  :

(  : 2 .L ,,_.. m ,

J>

. 3 - --- - - , .,

s N 7

-- .-, new w

• • PC 6C my R.DC W

&x sec E

\

L-j

~

-, n.

FOWc intm tyn

.\

' {- -

1 run ./ sec # wm W

Es ..

l g 5t0vst'v Otar*DL PDM ix mc - oc I

h,,

l Q =CMWc j ., y

\ /

I

\ .

i

. p

! ccm.at et 4:

I Y ' It t.s n I

Y '

9 C h e**<

}5.

\ E ml l'

\ '\

t D _

i

.\\

- I Tr  :

GW. ~;? .. a,l

• \

\

l x

ARLAS TO BE SURVEYED l i

g  :  : - rtNCE h -

I l

1 I

l I f

l - - - - - -

SECUPED APEJ. j i

N;i TO LCA r I i

i i

L r GupE 2: pothfinder Gene *oting Station - Survey Arcot, j 14 i i

.C'Q  :

1 1

t CCW4TROttCD ACC CS (NTRY $1ARway

-1 - -

l-. 6-.s 6..s <

s

.V' r

- Z

[ -

=

=

l - ._ ___  : -

r -

l 1 i lI ii r~n l l j s.s t

SPCNT FUCL POOL CMR l '

SPCNT FLC POOL ACCES5 NATCM

_ SEUD)

(

.I

'i

(

I m

_.}

l ==

STORAGE (PREMOUSLY

' :g* NEW FUEL w'. STORAGE ROOM) l i

I i

N 1

4 v

A NOT to St. ALE i i

l i i

l FIGURE 3: Fuel Handling Building Operating Floor 15 i

1

? ~Y 4 FEEDwaTIR OLTD5 c .,

I

. .g

$4m

.--lV '. .

--Fell 000 6 O is"ar- [

RESN - ,

twM -

SMELD DUNnD

($mD FLA.I0)

~

1 amu nLits '/ / )

.n sneto 1 euwta

j. r(!AND

.;.IID)

[ j-

-^

~'acectos l PUPACATION PRC-ntites

'l

- sotNT q rutL pcq RfyyD p----,

t D- ~

vacuX FImm

? / CD c- - - CD scr.ns "C'-

1*"

M 7"/, f4 t* ' Ntu1 % ctP NEUT M 12tp a p u m 14em WON RC9N 14Na acio puu a s i F-- . ...- CAT)ON RESIN ll *" %

5$es [". carcN etsr= auS 2' ff/. [ /,. l - , "RGT5"

(

. O I i

6 i

~

N l

J A

L

~/ INACCES$1BLE AREA h

NOT TO SCALC

.. a flGURE t.. Fuel Handling Building. Mezzonine soor l

l

}6 i

a

___j

PTX5 ,,

Orr cc C Ja.8PRt550#

==

YY _

U l SPtwf pts 8N TW

-- / - / 3 5_

s tacitpq PunincATioN gggg g gAj7ggg y

lJ 4 f o/ \oSI I p

CONP L V"P.AtID y t WASTI # I

$3 g g - - _ _

lf/ e ,. e r' /r"__ r. _ f staap Q P'* O

~

l 'CONCENTRA1TD 3pggy gggt g

'O'E S# POOL-CA$m AREA

- > - ~

es

, wCTE R CA"OR PURIOCAT10rd coottes

[ DE9e<tReurtp

,k

{_ . ,_Of L **xit. wla' EXCHAt4GtR et weetnau:ta

- j .. .

l l

1

'  %?*';"l

• y s

i DU otwNCRAu:Es0 I- PRtet.f r.R5

~

s; .

= 1 1 i

i t.o.

scu~is

/ '*/ '

l J M

=

O-tutpau2tp P

C U h- e L ggR;;(,3)uwe z tam 8 gg ,

I

, at.wlth

\ne l

N A

j st4 ACCESS 19;E APEA b

t401 10 SCALE w --

FIGURE 5: Fuel Handbng Building, E ciereent floor 17

rry:1 l

4

\

fREACTOR l BUILDING BJ LDING

_A

. l \ l l N li FUEL TRANSrER I TUBE N

I U

h NOT TO SCALE J

FIGURE 6: Fuel Transf er vcult 18

e -,

l

, i LJ m CL W 13e 1 1' ruCL putDNG r^SK CPAN[

\

L- 1

' l )J 6

+-,

P(P5QNN[L

'5 h neR LOCr CCNCC w'v. t v

• ST [ poRAct T 1 te E ' '

E5 9 ll oor_aater, rLp.

-...........; tuv 13;r

\

\ Se h=

4

. rm - -_

. x,o-swiar) , y- (,f -

l

- POOL u_;I -

[ 00:Pu00 TV -

l I ,' s *. j ~ [LD $ 3 t J-

, , l

i.l c=

Tr a N . ~~ Tf$$ll

[ .

\ -

l Rt.acice -

"[*' , ' .0, , I s t- <  ! vtrCL 73.aco , g_* -

f', l l s i m % 46 f

l SPENT CAlW % rVEL TRAN5f[R .I l

( ;: l RESN cwat !c sq1- 3 l

. ;f ' = 4~~~f  ;

e i y

~% I II i _. u,,n, v

.......Y.."....."....-

.....7

-l afv. 1251 FUEL HANDLING BUILD!NC P EACTOR CONTAINuCNT DUILDING l l

i N l I

l i

I i A

NOT T O SC ALE ,

i L I FIGURE 7: Reactor and fuel Handling Buildings, [levation VCD 19

=

r. . 7 l

i REACTOR BUILDING

%/

/ PERSONNEL gRErvtLING BRioGE N,\ FAIR LCCk i 1

'/\ '

T 3g gD POO,$ ^ SwtTCHCEAR i

e CRANE l

ACCCSS HATCH ,

(COVERED) ,

\ s/

i J

\ / I

\  !

EVERGENCY PERSONtdEL ,

AIR LOCK I N

$ l Sh  !

NOT 'O SCALE j i

FIGURE 8 Reactor Building. Ope'citng ricor 20 1

. Pt c I

f l

e ,

I '

c>ca.

l cmx ja x7e*pa w -onut g

/

x _

, / ,8 " m

?) *h V' l 9 rest

'?

fO O onsn O*"s

}

(

k cf O CfuNE

$ISE

[

/

\ etue scs /

h\ A= /

\' N'J se N

1 i

9 h

t.OT TO SejLE TICUPE 9 pe'JClor Building, Ecugrnent floor 21

, c t'. q, l

l

( -

1

/Ut cN eteica evumc m  %

V "yMD ES,7""

=:L ; y i s u

{etetoa nsstt

'l

\ //

/ '

I kQ

\I2r7ss N

1

+1 b

, no- o saa J

~ CURE 10. Reccto Eviicing. Plug Floor 22

I i I

. I I-l l

av om\

l

[

/ t .

^

f l

I =

/REU*Ctv%

PLD os

/ y

~:= -

\

to ')

I i e u -o  !

i l

\

Ox

'M c^. 7&s..'

ICT ll l'

l l

\'

x'x

% Sg' l l/}

i ey s lFJ !^u *

,/ l

\

/ '/ I.

4 ,

\ *f Cl*0VLA%

PM tam N

h 1 4r N

f401 TO SCALC FIGURE 11: Reactor Building. Pumo Floor 23

-~ ~'

.* rr, :

I N M- i

.L ii  %

,% ~

~~

[;, SECURED SAD w ASTE -

STOP. AGE ARE.A SECURITY

,; l; _

TENCE

i.

4  !'

. , l' ~

l

)

i!je

.i h.: , .

} j -

Il II i ,

l ll ll l -

1 NNxwwwwwwwxxsxxs i

N

{

1 I l 1 l

l

$ ry i* SCAtt 1-

.l t

TGUDF 12 T emovery i. coding cod Sto age Eu;icag a

__