IR 05000312/2008003

IR 05000312-08-003, on 09/08-11/2008, Energy Supply, Sacramento Municipal Utility District

ML082690356
Person / Time
Site:	Rancho Seco
Issue date:	09/24/2008
From:	Whitten J NRC/RGN-IV/DNMS/NMSBB
To:	Shelter J Sacramento Municipal Utility District (SMUD)
References
IR-08-003
Download: ML082690356 (57)

Text

September 24, 2008

SUBJECT:

DCN 1695-SR-03-1 (DOCKET NO. 50-312, RFTR NO.06-003)

Dear hdi. Hicktnan:

'I'he Oak Ridge Institute for Science and Education (ORISE) perforiiiccl conhnatoi-y siii-vcy ;ictiriiies 011 the ilusiha~y Building sti-uctural surfaces (Rooins 10, 15, 40, 42, 5 1 ;id 53), the Punip -r\\lley, the Fuel Storage Building esterioi: esc:~vation, and portions of the R;td \\Vaste :itid ilcmd Waste dratii systems a t thc Rancho Seco Nuclear Generating Station iti Hcrald, Cahfoniia on April 14 tliiough 17 atid hIay 29, 2008. These survey activities were requested arid approved by the U.S. Nuclear Regulatoq Corniilissioii (NlCC). Eiiclosed is a revised interim letter report to i.cplacc thc report, issucd on July 24, 2008, that coiltailled figures tha t mere misprinted. Tlus revised report suiiiinarizes ORISE's sumey proccdures and preliminary results of the confirmatory survey. ?'he surveys included beta arid gaiiuiin surface scans, chect measuremetits for total net beta activity, and smears for miiowhlc alplia and beta activit)r within die Alixiliary Building; embedded piping gamma scans within the Auslliarp Building; and litnited gainma scans and the colleclioii of soil saiiiples iti the Puiiip Alley and thc Fuel Storage Building exterior escavaf ion.

If you have any questions, please direct them to me at 865.576.0065 or Tiiii Vitkus at 865.576.5073.

ORISE Health Pltysicis t/Project Leader Siui~rey Projects Enclosure C:

'1'. Carter, N R C / T ; S h ~. / n ~ ~ ~, ~ P / D D / S P T-8F.5 E. Abclcluisi, ORISE E. IGios-Daviii, NRC/FShG/'ITWN 8A23 T. Youngblood, N R C / F S ~ i ~ / D \\ ~ ~ ~ P / ~ ~ ' F N 8 F5 E. Garcia, NRC/Region IY S. Roberts, ORlSG T. TTitkiis, ORISE File 1695 T70ice: 865.576.006.5 Fax: 865241.3497

REVISED INTERIM LETTER REPORT CONFIRMATORY SURVEY RESULTS FOR ACTIVITIES PERFORMED IN APRIL AND MAY 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA Prepared by

'CV.

C. Adains Prepared for the U. S. Nuclear Regulatory C oimnis sion AUGUST 2008 This report is based on worked performed by the Oak Ridge Institute for Scieiice and Education under contract number DE-AC05-060R23100 with the U.S. Departinent of Energy.

Rancho Seco Nuclcnr Gcncmting Stathn 1695-SR-03-I

REVISED INTERIM LETTER REPORT CONFIRMATORY SURVEY RESULTS FOR ACTIVITIES PERFORMED IN APRIL AND MAY 2008 RANCHO SECO NUCLEAR GENERATING STATION HERALD, CALIFORNIA INTRODUCTION The Sacramento hhnicipal U d t y District (SMUD) operated the Rancho Seco Nuclear Generating Station (RSNGS) from 1976 to 1989 under Atoinic Energy Coinmission Docket Number 50-312 and License Number DPR-54. In August 1989, SPIUD notified the U.S. Nuclear Regulatoi-y Coinmission (NRC) of the RSNGSs permanent shutdown. In Map 1991, SMUD subinitted the Rancho Seco Decominissioning Plan (DP) wl4ch \\vas approved by the NRC in blarch 1995. SMUD began decoimnissioning activities in Februaiy 1997 and completed transfer of all the spent nuclear fuel in August 2002 (SMUD 2006,).

In April 2006, SMUD subinitted a license termination plan (LTP) that the NRC approved on November 26,2007 (SMUD 20062 and NRC 2007). SMUD is currently conducting decontainiiiation efforts and performing final status suiveys (FSS) on the remaining structural surfaces and in open land areas.

The NRC requested that the Independent Environmental Assessment and Verification (IEAV)

Program of the Oak Ridge Institute for Science and Education (ORISE) perform confirmatoi-p suiveys of structural surfaces in several Aus&ai-~~

Budding rooins, the Pump Alley, the Acid Waste System aiid Rad Waste System drains in the Auiliaiy Budding and the Fuel Storage Building exterior excavation at the RSNGS (Figures 1 and 2). The confirmatory suiTreys were performed during the period of April 14 through 17 and May 29,2008.

PROCEDURES Confirinatoiy suiveys were performed in accordance with a site-specific suivey plan that was subinitted to and approved by the NRC (ORISE 2007a). The site-specific suiTrey plan follows the guidance provided in the IEAV Suivey Procedures and Quahty Program Man~als (ORISE 2008a and ORAU 2007).

In the Audai-y Building, ORISE perfoiined confirmatoiy sui-vey activities on structural surfaces in Rooins 10, 15, 40, 42, 51, 52, the 51 aiid 52 Excavation, and in the Pump Alley (Figures 3 through 15). ORISE performed suivey activities on the interior surfaces witliin two Acid Waste System drains (Figures 16 and 17) and hvo Rad Waste System drains (Figure 1s). At the request of the NRC site representative, ORISE also performed confirmatoiy ra&ological surveys of the Fuel Storage Building exterior excavation (Figure 19).

SURFACE SCANS Auxiliarv Buildinp Structural Surfaces Gainma surface scans were performed using sodium iodide, thakuin-activated PaI(Tl)] gamma scinullation detectors coupled to ratemeters with audible indmtors. Beta surface scans were 1695-SR-03-

Rnncho Scco Nuclear Generating Station

perfoimed using large area gas proportional, hand-held gas proportional, and Geiger-Muller (GfvlJ detectors coupled to ratemeter-scalers with aulble inlcators. Particular attention was given to cracks, joints, embedded piping openings and horizontal surfaces in the evaluated structural surfaces where inaterial may have accumulated.

Drains and Pipe Penetrations Limited qudtative gaimna scans were performed in portions of two Acid Waste Systein drain lines and in two Rad Waste Systein drain lines. Gaimna scans were performed using a cesium iodide, thallium-activated [CsI(Tl)] gainina scinttllation detector coupled to a ratemeter with an audible indicator. The detector was also paused at each one-foot scan increment and the garmna count rate recorded. These data were used for dxect comparison with the SMUD FSS data.

PumD Allev and Fuel Storape Buildinp Exterior Excavation Areas Gaimna scans of the soils witlin the excavated Pump Alley and the Fuel Storage Budding extedor excavation were performed using a NaI(T1) gaimna scinidlation detector coupled to a ratemeter with an audible indicator. Beta surface scans of the Puinp Alley concrete side walls were performed using hand-held gas proportional detectors coupled to ratemeter-scalers with audible indicators.

SURFACE ACTIVITY MEASUREMENTS Based on beta and gaimna surface scan results, direct measurements for beta activity were performed at 59 judgmentally-selected locations on the evaluated structural surfaces witlin the Auxhaiy Building which were available for confirmatoi-7 suivey activities; 11 direct measurement locations were performed within the Pump Alley. Direct ineasureinents mere performed using hand-held gas proportional detectors coupled to ratemeters-scalers. A sinear sainple for determining removable gross alpha and gross beta activity levels was collected froin each direct measurement location. Direct measurement and sinear locations are iiidicated on Figures 3 through 14.

SOIL SAMPLING ORISE collected four soil sainples based on gainina scan results during the initial confirtnatoiJT suivey activities of the Puinp M e y soil excavation in Apil2008. SfvIUD personnel performed gaimna spectroscopy on several of the sainples and deterinked that the soil derived concentration guideline levels (DCGLs) were exceeded and that further remedial actions would be required.

ORISE returned the four Puinp Alley soil samples to SMUD personnel as additional confirinatoq suivey activities of the Puinp Alley would be required. ORISE collected two judgmental soil sainples froin the Fuel Storage Building exterior excavation during the Apiil2008 suivey activities (Figure 19). ORISE collected three judgmental soil sainples froin the Puinp Alley excavation during the &lay 2008 suivey activities (Figure 15).

SAMPLE ANALYSIS AND DATA INTERPRETATION Ralological data and sainple media were returned to the ORISE laboratoi-y in Oak Bdge, Tennessee for analysis and interpretation. Radioassays were performed in accordance with the ORISE Laboratoi-y Procedures Manud (ORISE 2008b). The soil sainples were analped by gaimna Itancho Sccn Nuclcar Generating Statinn

1695-SR-03-I

spectroscopy for tlie primai-p ralonuclides-of-concern (ROC), cobalt-60 (co-60) and cesiuin-137 ((2-137). However, spectra were also reviewed for addtional gaimna-emitting fission and activation products associated with the RSNGS and other identifiable total absorption peaks. The soil sainple results were reported in units of picocuries per grain (pCi/g). Sinear samples mere analyzed for gross alpha and gross beta activity using a low-background gas proportional counter. Sinear results and direct measurements for total surface activity were converted to units of disintegrations per ininute per 100 square centimeters (dpm/l00 crn). Einbedded piping scan data were reported in units of counts per iniiiute (cpin) to compare with SMUDs gross gaiimia cpin FSS results.

FINDINGS AND RESULTS SURFACE SCANS The scan percent coverage and rooin area classifications are provided in Table 1.

Auxiliarv Buildinp Structural Surfaces Beta and gaimna surface scans determined that localized areas of residual elevated beta and gamiia radation were present on floor and lower wall surfaces within the evaluated sui-vey units (SUs).

Residual surface activity levels approaching site-specific DCGLs but less than the SU specific design DCGL elevated ineasureinent comparison (DCGL,,,c) were hnited to sinall areas that were interspersed throughout the rooins.

Acid Waste and Rad Waste Drain Svstems Gaimna scans of the Acid Waste and Rad Waste drains within the evaluated SUs indicated that gaimna radiation levels ranged froin 400 to 3,700 cpin. For coinparison, the CsI(T1) detector background range for the conduits along the east side of the Turbine Building at the +40 level elevation ranged from 200 to 800 cpin.

A comparison of ORISE and SMUD gaimna ineasureinent results for the Acid Waste System aiid Rad Waste System drain lines indicated elevated gaimna radiation levels at approximately tlie saine lengtli/depth and levels as reported by SMUD personnel in the preluninaiy FSS data packages. The ORISE conhrnatoqr aiid SMUD gaimna ineasureinent ranges are provided in Table 2.

PumD ALlev and Fuel Storape Buildiiw Excavation Areas Gaimna scans of the remediated portions of the Pump Alley and Fuel Storage Budding exterior excavation areas detected residual elevated gaimna radiation levels at several locations within the Pump Alley and did not detect any locations of elevated gainiiia radiation in tlie Fuel Storage Buillng excavation area. Beta scans of the Pump Alley concrete.walls indicated several locations of elevated residual beta radiation; these locations were inarked for further investigation.

SURFACE ACTIVITY LEVELS Surface activity and removable activity level results are presented in Table 3.

Ilanchn Scco Nuclear Gcncrating Station 1695-SR-03-I

Auxiliarv Buildiw Structural Surfaces Beta measurements were performed at locations of residual elevated beta and gaimna radiation detected during surface scans. Total net beta activity ineasureinents ranged froin 270 to 120,000 dpin/100 an2. Thirteen of the 59 direct measurements exceeded the DCGL but all were less than the specific SU DCGL,,,,,;. Removable gross alpha and gross beta activity ranged from 0 to 18 and-4 to 650 dpin/l00 an2, respectively.

Pump Alley Beta measurements were performed at locations of residual elevated beta and gamina radiation detected during surface scans. Total net beta activity measurements ranged from 6,300 to 52,000 dpm/100 an'. Two of the eleven direct measurements exceeded the DCGL but were less than the specific SU DCGL,,,,,. Removable gross alpha and gross beta activity ranged from 0 to 1 and-2 to 10 dpm/l00 cin', respectively.

SOIL SAMPLES The radionuclide concentrations for the two soil sainples collected within tlie reinediated portion of the Fuel Storage Building exterior excavated area ranged froin -0.01 to 0.00 pCi/g for co-60 and 0.42 to 0.44 pCi/g for Cs-137. The radionuclide concentrations for the three soil sainples collected withm the reinediated portion of the Pump Alley ranged froin 0.03 to 1.41 pCi/g for Co-60 and 0.38 to 121 pCi/g for Cs-137. The confirinatoiy radionuclide concentrations for the soil samples are provided in Table 4.

COMPARISON OF SURVEY RESULTS WITH GUIDELINES STRUCTURAL SURFACE ACTIVITY LEVELS The major containinants identified by SMUD at RSNGS are beta-gamma emitters-fission and activation products-resulting froin reactor operation. Cs-137 and co-60 have been identified during characterization as the predominant radionuclides present on structural surfaces. SMUD developed site-specific DCGLs, wlich were recently approved by the NRC, based on a dose modeling to future occupants not to exceed 25 inrein/year total effective dose equivalent (TEDE) as presented in Section 6 of the L'I" (SMUD 2006a and NRC 2007). The DCGLs for surfaces were modified by SMUD to reflect tlie ratio of radionuclide concentrations (account for tlie presence of unineasured containinants based on coiltaminant ratios) in the specific SUs that were being evaluated. The applicable surface activity guidelines for the evaluated structural surfaces for these suiveys are provided in Table 5. These DCGLs were provided in tlie preluninai7r FSS data packages for each evaluated SU and were derived from the LTP and decoiniissioning teclinical basis document (DTBD)-05-015 (SMUD 2006a and b).

Confuinatoi-p suivey data for Auslliaiy Budding structural surfaces were coinpared with the site-specific DCGL for the evaluated Auxlliaiy Budding SUs. Of the 70 direct beta activity measurement results on the concrete sti-uctural surfaces, 15 exceeded the Gross Beta DCGL of 43,000 dpm/100 an'. Using the gross activity DCGL as determined in DTBD-05-015 (SMUD 2006b) and the area factor deteilllined for each SU, SMUD calculated Design DCGL,,,,,

lianchc Seco Nuclear Gcncmtlng Stxion

/l T

values which are also provided in Table 5. All confirinatoiy lrect surface activity measurements on the A u d a i y Budding sti-uctural surfaces in the evaluated SUs were witlin the site-specific SU DCGL,,,,

as provided by SMUD in the prelirmnaiy FSS data packages.

ACID WASTE AND RAD WASTE DRAIN SYSTEMS CO-60 is the priinalry ROC.iYithm the embedded piping. SMUD has established a dose-based restriction for embedded piping not to exceed 25 inrein/pear that assuines a budding occupancy scenaiio witlin rooins where embedded piping is present. The corresponding modeled DCGL is 100,000 dpm/100 an2. SMUDs grouting action level for embedded piping is 21,000 dpin/100 cin (SMUD 2007).

ORISEs confirinatoiy drain line results were not directly coinpared to the embedded piping DCGL; instead, since ORISE and SbIUD used skntlar CsI(T1) detectors (Ludluin Model 41-159),

ORISE compared gross gainma scan realngs with either SMUDs prehniiiaiy FSS data package gaimna scan results for each suiveyed pipe at various depths or with background levels as determined during a previous ORISE conflt-matoy suivey (ORISE 2007b).

Confinllatoq suivey data for the Acid Waste and Rad Waste Systein drain lines were coinpared wit11 the prehninai77 FSS data package gross gaimna cpin results. The confirinatoiy gainina scan results indicated that ORISE gross g a i m a ralation levels within tlie drain line pipes were consistent with the SNIUD prelu-ninaq FSS data package results.

SOIL SAMPLES Table 6-5 (Table 6) from the LTP provides the single nuclide DCGLs for soil at RSNGS. The DCGL is 12.6 pCi/g for CO-60 and 52.8 pCi/g for Cs-137 (SMUD 2006a). The Fuel Storage Budding esterior escavation area soil sample concentrations were below the respective single radionuclide DCGLs. Two of tlie three conhrinatory soil samples from the Puinp Alley were well below the single nuclide DCGL; however, one soil sample (1695S0016 containing 121 pCi/g of Cs-237) esceeded the soil DCGL for (3-137 but was witl?in the soil DCGL,,,, for tlie SU wlich was calculated by SL\\/IUD to be 189 pCi/g.

SUMMARY During the period of April 27 tlirough 29 and May 29,2008, ORISE performed confirinatoiy radiological suwey activities which included beta and gaimna surface scans, beta activity direct measurements, and removable gross alpha and gross beta activity measurements on structural surfaces witlin the Austliaiy Building; gaimna scans within Auxhaiy BLullng Acid Waste and Rad Waste drains; and gamna scans and the collection of soil samples from the Puinp Alley and Fuel Storage Building escavation areas.

Beta and gaiimia surface scans identified several areas of elevated beta radiation on the structural surfaces of the evaluated SUs within the Auxha1-y Building. Additional investigations of these locations indicated that the majority of the elevated radiation levels were attributable to localized areas of residual beta-gaimna radiation within the inatiis of the concrete media. In general, the elevated surface activity was IImited to sinall areas that were interspersed throughout the rooins.

Rancho Scco Nuclcnr Gcncrating Station

Direct measurements were performed at 70 locations. Fifteen direct measurements exceeded the site-specific gross beta DCGL but aV were witlin the SU specific design DCGL,:,,, criteria. The confEinatoiy suivey results for Rooms 10, 15, 40, 42, 51, 52 and the Pump Alley concrete walls are in agreement with the radological status of these SUs as presented in the licensee's preluninai-y FSS data packages.

Confirmatoi-p gainma surface scans of the evaluated Aunhary Budding drain systems indcated that the gainma radation levels were consistent with the results presented in the preluninaiy FSS data packages for the suiveyed drains.

The soil sample results froin the Fuel Storage B d d n g esterior excavation area were below the individual radonuclide DCGLs and meet the soil release criteria. One of the three soil samples from the Pump Alley exceeded the soil DCGL for Cs-137; however, this sample was within the SU specific design DCGL,:,,,: for Cs-137.

Ilancho Scco Nuclcar Generating Station h

1695-SR-03-1

FIGURES Rancho Scco Nuclcar Gcncrating Station

N f

N( )TIT) s(.Ar.b:

Figure 1: Location of Rancho Seco Nuclear Generating Station, Herald, California S

695-002 ( 2 )

i SI'IZhY I'ONDS f m i

r-

- --

N I

NOT TO SCALE Figure 2: Plot Plan of the Industrial Area at Rancho Seco Nuclear Generating Station I<ancho Scco Nuclear Gcncrating Staticin

I North Wall Figure provided by SMUD.

South wall ICIEASURE1CIENT/SAMLE LOCATION Single Point, Floor and Lower Walls

Floor N - 4

~

NOT TO SCALE Figure 3: Survey Unit FS130101, Rooin 10 - Direct Measurement aiid Sainple Locations RnncIi[i Scco Nuclear Gcncratrng Statlrrn

1635-Slt(13-1

MEASURETVlENT/SAMPLE LOCATION Single Point, Floor and Lower Walls

Rancho Scco Nuclear Ckncrating Station

-

AT-NOT TO SCALE

1695-SR-03-I

f I

Figure provided by %IUD MEASUREMENT/SAblPLE LOCATION x Single Point, Floor and Lower W d s N

or -

NOT TO SCALE Figure 5: Sumep Unit F8130541, Room 40 - Direct bleasureinent and Sainple Locations ltancho Scco Nuclcnr Gcncratlng Station

Figure provided by SMUD.

MEASURETVLENT/SATVPLE LOCATION Single Point, Floor and Lower Walls

1. Single Point, Upper Surfaces

--mc N 4 NOT TO SCALE Figure 6: Survey Unit FS1305S1, Rooin 42 - Direct Measurement and Sainple Locations Itnncho Scco Nuc1e:ir Gcnerating Station

Figure provided by SLIUD.

MEASUREMENT/ SAhfPLE LOCATION Single Point, Floor and Lower Walls

1. Single Point, Upper Surfaces NOT TO SCALE I

Figure 7: Suivejr Unit F8130169, F8130701 and F8130711, Room 51, Section 1 -

Direct Measurement and Sample Locations Rancho Scco Nuclear (hicrating Station

Figure provided by SMJD.

MEASURETvlENT/SATvPLE LOCATION ff Single Point, Upper Surfaces

rc B-N NOT TO SCALE Figure S

Sumey Unit FS130701, Room 51, Section 1, Upper Surfaces -

Direct Measurement and Sample Locations

Rancho Secn Nuclcar Generating Stnttnn

I North Wall

H MEASURETVIENT/SAMTLE LOCATION e-

&>&

AT-

,I

Single Point, Floor and Lower Walls

NOT TO SCALE Figure 9: Suivey Unit F8130701 and F8130711, Room 51, Section 2 -

Direct Measurement and Sample Locations

2-hleter Line North Wall West Wall Figure provided by SAlUD.

MEASUREMENT/SATLE LOCATION tt Single Point, Upper Surfaces U

Overhead Structure Column N -a jl' -

NOT TO SCALE Figure 10: Survey Unit F8130721, Rooin 51, Section 2 -

Direct Measurement and Sample Locations Rancho Scco Nuclear Cherarlng Stnilon

1695-SR-03-I

I I

Eks -20-D Figure provided by SRIUD.

RX Wall IvIEASUREMENT/SALLE LOCATION Single Point, Floor and Lower Walls

A NOT TO SCALE Figure 11: Suivey Unit FS130732, Rooin 51 and 52 Excavation -

Direct Measurement and Sample Locations I<ancho Seco NLIC~CX Generating Station 1s 1695-SI<-03-I

Figure provided MEASUREMENT/SAMPLE LOCATION Single Point, Floor and Lower Walls

1. I

\\

I i

I A

NOT TO SCALE Figure 12: Suivey Unit F8130751, Room 52, West of Column N -

Direct Measurement and Sample Locations Ihclio Scco Nuclcar Gcncratmg Statton

Figure provided by SMUD.

MEASURETVIENT/ SAMFLE LOCATION Single Point, Floor and Lower Walls A

NOT TO SCALE Figure 13: Sui-vey Unit FSl30761, Room 52, East of Column N -

Direct Measurement and Sample Locations Itanclx Scco Nuclear Gcncratmg Statmn

. _

Figure provided by SAIUD.

TVIEASUREMENT/SAMPLE

\\

I LOCATION Single Point, Floor and Lower Walls

NOT TO SCALE Figure 14: Suive-p Unit F8130461, Pump Mey - Direct Measurement and Sample Locations Ilancho Scco Nuclcar GcncratinS Stntion

Figure provided by SMUD.

SOIL SAMPLE LOCATION

1. Soil Sample N O T TO SCALE I

Figure 15: Suivey Unit F8130121, Pump Alley - Soil Sample Locations Ilancho Scco Nuclcnr Gcncrntmg Statlon

i Figure provided by SAKJD.

TVIEASUREMENT LOCATION I\\

I A

I NOT TO SCALE Figure 16: Suwey Unit F8990521, Acid Waste Drains - Sumeyed Drain 4-1-1 1 Ilancho Scco Nuclear Gcncratmg Station

iYIEASUREiYIENT LOCATION ul Surveyed Drain Figure 17: Suivey Unit F8990521, Acid Waste Drains - Sui-tieyed Drain 4-2-4 N --

JiL-I l l --

NOT TO SCALE I<nncho Scco Nuclcnr Gcncratlng Statlon

MEASUREMENT LOCATION N 4-

"1 N O T TO SCALE 111 -

I Figure 18: Sumey Unit F8990521, Rad Waste Drains - SumejTed Drains 2-1-9 and 2-1-14

1695-SR-03-I

Fuel Storage Building 1i 1 '1 Diesel Generator Room Figure provided by SMUD.

I Containment m SE corner of p Auxitiarv Building SOIL S A W L E LOCATION

1. Soil Sample 1v I

A NOT TO SCALE Figure 19: Survey Unit F8130101, Fuel Storage Bddmg Exterior Excavation -

Soil Sampling Locations

Rancho Scco Nuclcar Generating Stauon

TABLES

Ilicfcr to Figures 3 through 15 and 19. IT. = floor, I,\\V = lower wall niid US = lipper surfaces

'6cans not performed.

CGaintna surfacc soil scans of excavations.

lkmcho Scco Nuclear Gcncrating Stntion

Conduit, East Side 1 Conduit. East Side 2 Conduit, East Side 3 Conduit, East Side 4 Penetration, East Side Exciter Pad East Exciter Pad West Background Range

"

v Auxiliary Building AN 4-1-11 b

I 300 to 600 I

_ _ _

I

I

1 300 to 600

4

200 to 600

-__

1 300 to 600

-__

1 300 to 600

___

12 200 to so0

--_

12 200 to 800

--_

--_

-__

200 to 800

___

I I

I Gamma Measurements (cpin)"

d Waste Drainsd

400 450

400 510

500 510

400 500

500 520

500 520 I

I 400 I

550 I

I 500 I

510 I

I 500 I

510

I

I 500 I

560 I

I

I 500 I

540 I

I 400 I

450 I

I 400 I

530 I

500 520

400 510

500 550

400 480

400 510 I

I 500 I

540 I

I 500 I

540 I

I 400 I

510 11:?5-S!? 03- !

a/

Rancho Sccn Nuclcar Generating Statirrn

4-2-4 Auxiliary Building R 2-1-9 Di arneter Scan Length Gamma Measurements (cpin)'

ORISE SMUD (inches)

(feet)

d Waste Drainsd I

I 2,900 I

2,500

400 370

400 41 0

500 400

400 440

500 I1 0

500 420

400 350 I

S I

500 I

41 0

500 420

500 380

11 500 390

400 330

500 400

500 360

400 400

400 390 I

I 400 I

400

400 390

400 41 0

400 41 0

500 410

400 370 I

I I

3 Waste Drainsd

3,100 3,600

1.100 2.300

700 1,100

3 500 500 I

I 500 I

1,000

900 1,400

2,400 2,900 1695-SR-O? I

?fl 4"

Rancho Seco Nuclear Generating Station

2-1-14

7 1,900 2,400

1,100 1,900

700 1,400

1,000 1,400

so0 1,300

so0 1,200

1,000 1,400

800 1,300 2-1-9 (continued)

1,000 1,500

1,000 1,500

1,000 1,600

1,000 1,600

1,100 1,500

1,100 1,500

so0 1,200

700 1,000 I

I

?I 16'?5-,EI? (!3-1

- *

Rnncho Seco Nuclear Gencmting Station

Drain Line Diameter Scan Length Gamma Measurements (cpm)'

Location (inches)

(feet)

OFUSE SMUD Auxiliary Building Rad Waste Drainsd 2-1-14 (continued)

2,500 3,000 2,300 2,200 2,800 2.900 2,600

20

Turbine Buildi~ig cmbcddcd piping backgrounds wcrc detcriiiincd within Turbine Building conduits. 'Fliis data was collected duriiig a previous OliISE survey (OllIS13 2007b).

"Mcasurcmcnts not perforiiicd by SMUD witliiii the Turbine Building conduits.

cSMUD gamma scan rncasuccmcnt data was provided to ORISE in preliminary IFSS data pacltagcs or during comparison gainma incas~ircinciits inadc with similar gainina dctcctors. ORISE and SMUD results ~ e r c rouiidcd to two sigiificniit digits.

dRefcr to Figurcs 16 tlirougli 18.

Rancho Scco Nuclcnr Gcncrnting Station

1695-SR-03-I

Auxiliary Building, Room 10

FL 9,800

16 YES

LW 6,500

8 YES

FL 7,400

8 YES

FL 31,000

84 YES

L\\V 7,800

46 YES G

I LW I

9.900

190 Y E S I

I I

I I

I

-

- __

Auxiliary Building, Room 15

FL 8,700

76 YES

FL 1 1,000

2 YES

FL 11,000

6 YES

FL 21,000

2 YES

FL 37,000

-4 YES

FL 20,000

-3 YES

TCV 14,000

-1 YES

FL 16,000

1 YES

L\\V 30,000

14 YES

LW 16,000

1 YES

LW 34,000

1 YES

I FL 53,000 I

110 NO

FL 9,500

34 YES

FL 12,000

2 YES

FL 8,000

-3 YES

US 6,600

36 YES Ilancho Scco Nuclear Gcncrating Stntirin

Rancho Scco Nuclcnr Gcncrating Station

Total Beta Removable Activity Activity Meets Room/

surface Activity (dpm/100 cm)

Gross Beta Location (dpm/100 ern')'

Alpha Beta DCGL~

Auxiliary Building, Room 52 I

I I

I i

FL 56,000

14 NO

FL 10,000

-2 YES

FL 54,000

-1 NO

FL 35,000

3 YES

FL 13,000

-1 YES

FL 27,000

-3 YES

~~~~

L\\V 61,000

200 NO

L\\V 64,000

190 NO I

I LW I

14.000 I

I

1 YES I

I I

I

~

~~

~

Auxiliary Building, Pump Alley I

G LW 10,000

1 YES I

I I

I

7 LW 1 1,000

I YES

LW 12,000

2 k%S

LW 13,000

1 YES

L\\V 10,000

10 YES I

I LW I

15.000

0 I

1 YES

lRcfcr to Figures 3 through 14.

&Structural surfaces; FL = floor, I,W = lower wall, *IT7 = trench waU and US = upper surfaces.

cl)ircct iiica~i~rerncnt resdts rounded to hvo sipificant di&.

dDCGL values are provided in Table 5. A U surface activity iiieawrcinciits that were greater tlian the gross beta DCGL wcrc less than the dcsigi DCG1.s dctcrtniiicd for cadi spccific survey uiiit.

Rancho Scco Nuclear Gencrattng Station 16%-SIl-03-I

Ilicfcr to Figures 15 and 19.

'Wnccrtaintics represent the 95% confidence level based on total propagated unccrtaintics.

CZcro values arc due to rounclitig.

Auxiliary Building Gross Beta DCGLb Design DCGL,,,,'

Survey Unit/Room" (dpm/100 cm2)

(dpm/100 cm')

Class

.

10FLandLW

1 I

43,000 I

224,000 15 FLandLLV I

I 43,000 I

152,400 40 FL and LW

43,000 141,900 42 FL and LTV

43,000 141,900

'Refer to 17iguics 3 through 14 FI, = floor, LLV

')Gross beta DCGI, accounts foi iadtonuchdc fractions and hard to detects as spectficd ui the DT13D-05-15 (SIVIUD 2006b)

LDCGI-.C~IC piovided by SMUD and accounted for area factors dcteriniiicd fot each specific sulvcy iinit.

lowei wall and US = upper surfaces Rancho Scco Nuclcar Generating Station

1695-811-03-1

~(lnblc 6-5 froin tlic Liccnsc Tcrmi~iatro~i Plan (SIvIUD 2006,)

Ilancho Seco Nuclcnr Gcncrating Station

1695-SR-03-I

REFERENCES Oak Rtdge Associated Universities (OlL4U). Quality Program Manual for the Independent Environmental Assessment and Verification Program. Oak Rtdge, Tennessee; November 1,2007.

Oak Rtdge Institute for Science and Education (ORISE). Final Confumatoiy Suivep Plan for the Remaining Structural Surfaces, Embedded Piping, Standmg Water and Open Land Area Suivey Units, Rancho Seco Nuclear Generating Station, Herald California pocket No. 50-312; RFTA No. 06-0031. Oak Rtdge, Tennessee; August 10,2007a.

Oak a d g e Institute for Science and Education. Revised-Confirinatoq~ Sumep Report for Portions of the Au4daiy Building Structural Surfaces and Turbine Budding Embedded Piping, Rancho Seco Nuclear Generating Station, Herald, Cdfornia. DCN 1695-SR-01-1. Oak Rtdge, Tennessee; December 21,2007b.

Oak Rtdge Institute for Science and Education. Survey Procedures Manual for the Independent Environmental Assessment and Verification Program. Oak Rtdge, Tennessee; May 1,2008a.

Oak Rtdge Institute for Science and Education. Laboratoqr Procedures Manual for the Independent Environmental Assessment and Verification Program. Oak Rtdge, Tennessee; March 3, 2008b.

Sacrainento Municipal Utility District (SMUD). License Termination Plan, Rancho Seco Nuclear Generating Station, Herald, Cahfornia; Apiil2006a.

Sacramento Municipal Uultty District. Decoininissioning Technical Basis Document: Structure Nuclide Fraction and DCGLs. DTBD-05-015, Revision 0. Rancho Seco Nuclear Generating Station, Herald, California; June 2,2006b.

Sacramento Municipal Utillty District. Decoimnissioning Teclinical Basis Document: Embedded Piping Scenario and DCGL Deterinination Basis. DTBD-05-009, Revision No. 1.O. Rancho Seco Nuclear Generating Station, Herald, Cahfornia; June 1,2007.

U.S. Nuclear Regulatory Cormnission (NRC). Letter froin J. Hickman (NRC-HQ to S. Redeker (SMUD); SUBJECT Rancho Seco Nuclear Generating Station - Issuance of Amendment RJ3:

License Terinihion Plan (TAC No. J52668). Waslxngton, DC; November 27,2007.

liancho Scco Nuclear Gencroting Station

1695-SR-03-I

Sacramento Municipal Utility District-4-cc w/e ncl os u re ATHowell CLCain J BH ickman, FSM E/DWM E P/DU RLD THYoungblood, FSME/DWMEP/DURLD ACMcMurtray, NSIR/DPR/DDEP/LI JEWhitten EMGarcia RKella r Fees R : /-D N M S/-RS/2008 ML SUNS1 Review Complete: EMG ADAMS: mYesoNo Initials: EMG

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