ML091670511

Phase Release of Site

ML091670511
Person / Time
Site:	Rancho Seco
Issue date:	06/08/2009
From:	Ronningen E Sacramento Municipal Utility District (SMUD)
To:	John Hickman Document Control Desk, NRC/FSME
References
DPG 09-006
Download: ML091670511 (55)

Text

0 SMUD L[

SACRAMENTO MUNICIPAL UTILITY DISTRICT The Power To Do More.'

P.O. Box 15830, Sacramento, CA 95852-1830; 1-888-742-SMUD (7683)

DPG 09-006 June 8, 2009 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 PHASED RELEASE OF THE RANCHO SECO SITE Attention: John Hickman The purpose of this letter is to request that the Nuclear Regulatory Commission (NRC) release a portion of the Rancho Seco site from 10 CFR Part 50 License Number DPR-54.

The area to be released encompasses the majority of the Rancho Seco site. The only area remaining under the 10 CFR Part 50 license will be the Interim Onsite Storage Building (IOSB) which provides interim storage for radioactive waste. The IOSB is surrounded by a fence that defines the boundary of the remainingl 0 CFR Part 50 site. The spent nuclear fuel remains stored at the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI) licensed under 10 CFR Part 72.

The NRC approved the Rancho Seco License Termination Plan (LTP) on November 27, 2007. LTP Section 1.4.2 discusses SMUD's intent to release the Rancho Seco site for unrestricted use in two phases. We have now completed the first phase of Rancho Seco decommissioning and are requesting that the NRC release a major portion of the Rancho Seco site for unrestricted use.

SMUD has reviewed the survey area results to ensure that the proposed action will have no adverse impact on the ability of the site, in aggregate, to meet 10 CFR Part 20, Subpart E criteria for unrestricted use.

RANCHO SECO NUCLEAR PLANT

• 14440 Twin Cities Road, Herald, CA 95638-9799; (209) 333-2935

.0 provides a summary of the assessment performed. Attachment 1.0 does not contain the Final Status Survey (FSS) reports for all of the subject survey areas because those reports were submitted to the NRC previously..0 contains the post FSS particle survey results performed at Rancho Seco.

Attachments 3.0 and 4.0 presents an evaluation of the Co-60 and Cs-137 nuclide fraction in FSS soil samples and structure surfaces, respectively. These evaluations were also requested by your staff.

Members of your staff with questions requiring additional information or clarification may contact me at (916) 732-4817.

Sincerely, Einar Ronninn Superintendent, Rancho Seco Assets Attachment Cc: Elmo Collins, NRC, Region IV 2

Attachment I Release of Rancho Seco Land from the 10 CFR Part 50 License

,1.0 Introduction Rancho Seco Nuclear Generating Station was a 913-MWe PWR designed by Babcock and Wilcox Company. SMUD shut down Rancho Seco permanently on June 7, 1989, after approximately 15 years of operation. On August 29, 1989, SMUD formally informed the NRC that the plant was shut down permanently.

On May 20, 1991, SMUD submitted the Rancho Seco decommissioning plan and on March 20, 1995, the NRC issued an Order approving the decommissioning plan and authorizing the decommissioning of Rancho Seco. In March 1997, SMUD submitted its Post Shutdown Decommissioning Activities Report (PSDAR), in accordance with 10 CFR 50.82. The PSDAR superseded the original Decommissioning Plan and provided the information required by 10 CFR 50.82(a)(4).

SMUD began actively decommissioning Rancho Seco in February 1997, and the NRC approved the License Termination Plan (LTP) on November 27, 2007.

SMUD completed transferring all of the spent nuclear fuel to the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI), under the site-specific 10 CFR Part 72 license, on August 21, 2002, 2.0 Evaluation 2.1 Areas to be Released and FSS Results The area that we are requesting to release consists of the following general survey.areas noted below. These survey areas encompass the majority of the site leaving only the IOSB fence-line within the 10 CFR Part 50 licensed site. The specific survey units to be released are presented in Table 1.0. Table 1.0 includes the Survey Unit identification code, name, survey class, survey type, submittal number, and area in m2.

Area ID #: 100000 Survey Area: Plant Effluent Water Course Operating History: This area comprising 42,315 m2 located at the south west comer of the site was the release point for liquid effluents generated by the plant. It includes the land on both sides of the creek. Portions of the area (approximately 21,483 M 2) were impacted by both planned and unplanned liquid releases as well as the planned dispersion of dredged stream sediment. Operating records and the HSA document the release of radioactivity in this survey area. The HSA recorded multiple unplanned release events.

(The Annual Environmental Report submitted to the NRC in 2002 contained the results of soil/sediment samples collected from this area.)

3 Release of Rancho Seco Land from the 10 CFR Part 50 License Effluent activity and dose to the public were monitored and reported under the operating RETS/REMP program. Because the creek itself is beyond the site release point, it is outside the scope of FSS.

Area ID #: 200000, Survey Area: South Plant Outfall Operating History: The area extended from the south Industrial Area fence to the South Non-Impacted Area and covered 226,567 in 2. It bordered the Plant Effluent Water Course area to the west. Operating records and the HSA document several unplanned release events from the RHUT with the potential to contaminate the area.

Area ID #: 300000 Survey Area: South Non-Impacted Area Operating History: This area bordered the Plant Effluent Water Course to the west. The area extended from the South Plant Outfall Area to the southern boundary of the site and 2

contained approximately 306,000 m. Operating records and the HSA document no release of radioactivity in this survey area. The HSA recorded no unplanned release events.

Area ID #: 400000 Survey Area: South East Non-Impacted Area Operating History: This area comprised the entire south-east comer of the site. It bordered the Industrial Area, Area 200000, and Area 300000 to the east. The area extended south from the site access road and contained approximately 667,000 M2.

Operating records and the HSA document no release of radioactivity in this survey area.

Area ID #: 500000 Survey Area: North East Non-Impacted Area Operating History: The area extended from the Industrial Area fence to the plant access road (exclusive of the parking lots, roadway and warehouse in this area) making up the north-east quadrant of the site. It contained approximately 549,000 in2. Portions of the Upper/Outer Yard, Receiving Warehouse, Extended Parking Areas and Site Access Roadway (96,280 M2) were used to stage, transport and receive radioactive material.

Operating records and the HSA document no release of radioactivity in this survey area.

The HSA recorded no unplanned release events.

4 Release of Rancho Seco Land from the 10 CFR Part 50 License Area ID #: 600000 Survey Area: North Non-Impacted Area Operating History: The area extended from the Industrial Area fence north to state highway 104 (exclusive of the rail line in this area) and west to the site boundary. It 2

contained approximately 233,000 m.

Operating records and the HSA document no release of radioactivity in this survey area. The HSA recorded no unplanned release events.

Area ID #: 700000 Survey Area: West Non-Impacted Area Operating History: The area extended from the Industrial Area fencewest to the site boundary (exclusive of the ISFSI and rail line in this area). It covered approximately 229,000 m2. Operating records and the HSA document no release of radioactivity in this survey area however this area does border the effluent discharge area. The HSA recorded no unplanned release events.

Area ID #: 800000 Survey Area: Industrial Area Soils Operating History: The area covers the Industrial Area land (both bare soil and paved areas) exclusive of the building footprints and rail line in this area. The survey units for the region comprise approximately 357,268 in 2. Operating records and the HSA document no specific release of radioactivity in these survey areas however this area does border known contaminated areas. Specific locations in this area that contained radioactive waste or effluent include the Barrel Farm and Retention Basins. The HSA recorded no specific unplanned release events.

The area identifications listed above (100000-800000) were illustrated in Chapter 2 of the License Termination Plan as Figure 2-3. A copy of this map is provided below.

5 Release of Rancho Seco Land from the 10 CFR Part 50 License 800000 I

600000",

I II I-----------------7

/

500000 Li700 00p,1 I

,I II*

.I 1 1000[

,9-2*00000 400000 7 -------

II--

I I

II 3000.0-SAM*UO F Figure 2-3 SCMU Area Designations UTCLIE DiSTRUCT

.U 6

Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 Area 100000 Effluent Corridor F11000001 Effluent Corridor 2

Soil 3

8339 F1000002 Effluent Corridor 2

Soil 3

7744 F 1000003 Effluent Corridor 2

Soil 3

5202 F 1000004 Effluent Corridor 1

Soil 3

198 Area 200000 South Outfall F2000001 South Outfall 3

Soil.

3 226567 Area 500000 North East of Industrial Area F5010011 Receiving Warehouse Ext 3

Structure 1

1177 F5010012 Receiving Warehouse Int 3

Structure 1

1531 F5010031 Upper/Outer Yard 3

Soil 3

2665 F5010032 Hazardous Waste Bld Pad 3

Structure 3

268 F5010041 Extended Parking Area 3

Soil 3

42735 F5010042 Extended Parking Area 3

Soil 3

38692 F5010051 Site Access Roadway 3

Soil 5

9210 Area 800000 Miscellaneous Site Soils F8000011 Helo Pad 3

Soil 4

17284 F8000041 Central Transit Yard 3

Soil 3

6634 F8000071 West Industrial Area 3

Soil 3

88190 F8000072 Industrial Area West (West of Barrel Farm) 3 Soil 5

696 F8000073 Industrial Area West (North End) 3 Soil 5

255 7

Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit-SUID#

SU Name Class Type Number Size m2 F8000091 South East Industrial Area 3

Soil 5

55736 F8000101 Industrial Area Central Yard, North and East of Maintenance Building 3

Soil 5

1587 F8000102 Industrial Area Central Yard, North and West of Maintenance Building 3

Soil 5

1800 F8000103 Aux Bld/NSEB Alley 3

Soil 4

443 F8000104 Pump Alley Access Corridor 1

Soil 5

248 F8000105 Industrial Area, North-South Roadway East of BWB 2

Soil 5

1696 F8000106 Central Industrial Area Roadway 2

Soil 5

3680 F8000111 Industrial Area Corridor, North of "A" Warehouse and Fab Shop 2

Soil 5

1086 F8000121 Industrial Area Yard Buffer 3

Soil 3

6114 F8000141 North Industrial Area 3

Soil 3

55761 F8000142 North Industrial Area 3

Soil 5

29138 F8080031 Cooling Tower Buffer South 2

Soil 5

7500 F8080032 Cooling Tower Buffer West 2

Soil 5

5547 F8080033 Cooling Tower Buffer East 2

Soil 5

6481 F8090011 Sewer Plant Pavement 3

Soil 2

262 F8390001 Transformer Yard 3

Soil 3

3385 F8430011 Barrel Farm 1

Soil 3

1313 F8430021 Barrel Farm Surface Soil 2

Soil 3

5000 F8480011 N Retention Basin 1

Soil 3

1432 F8480012 S Retention Basin 1

Soil 3

1388 F8480017 Retention Basin Surf Soil 3

Soil 3

3590 F8480018 Retention Basin Concrete Structure 2

Soil 3

1059 F8480021 Retention Basin Buffer 3

Soil 3

10845 8

Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8510001 Switch Yard Soil 3

Soil 3

16700 F8510002 Switch Yard Pavement 3

Soil 3

14505 F8510005 Switch Yard South (plus Retention Basin Buffer) 3 Soil 5

7913 Area 800000 Miscellaneous Site Structures F8040011 PAP Bld Exterior 3

Structure 1

1177 F8040012 PAP Bld Interior 3

Structure 1

836 F8050011 Admin Bld Interior 3

Structure 1

910 F8050012 Admin Bld Exterior 3

Structure 1

1705 F8080011 E, W Cooling Tower Basins 3

Structure 2

47415 F8140002 T&R Bld Exterior 3

Structure 1

4303 F8140003 Training and Records Building Breezeway 3

Structure 5

431.4 F8140010 T&R Bld Interior 3

Structure 1

22160 F8150011 NSEB Interior 3

Structure 1

1197 F8150021 NSEB Exterior 3

Structure 1

1609 F8170011 Diesel Gen Bld Interior 3

Structure 1

3267 F8170021 Diesel Gen Bld Exterior 3

Structure 1

3484 F8210001 Water Treat Bld Interior 3

-Structure.

1 416 F8210002 Water Treat Bld Exterior 3

Structure 1

392 F8220011 Chlorine Bld Interior 3

Structure 1

597 F8220021 Chlorine Bld Exterior 3

Structure 1

457 F8230001 Intake Structure 3

Structure 3

402 F8240001 Primary Cooling Water Structure 2

Structure 2

252 F8310001 Microwave Bid Interior 3

Structure 1

274 9

Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8310002 Microwave Bld Exterior 2

Structure 1

146 F8320001 Diesel Fuel Oil Tank Pad 3

Soil 3

1560 F8330001 Warehouse B Interior 3

Structure 1

3182 F8330002 Warehouse B Exterior 2

Structure 1

2574 F8400001 Warehouse A Interior 3

Structure 1

4548 F8400002 Warehouse A Exterior 3

Structure 1

1972 F8480013 Discharge Boxes/Manholes 1

Structure 2

124.3 F8480014 Discharge Boxes/Manholes 1

Structure 2

145.2 F8480015 Discharge Boxes/Manholes 1

Structure 2

26.8 F8480016 Discharge Boxes/Manholes 1

Structure 2

137 F8480019 Misc Small Buildings Retention Basin Area 3

Structure 4

242 F8510003 Switch Yd Bld Exterior 3

Structure 1

543 F8510004 Switch Yd Bid Interior 3

Structure 1

1374 F8520001 Machine Shop Interior 3

Structure 1

1482 F8520002 Machine Shop Exterior 3

Structure 1

952 F8540001 Misc Small Blds POL 3

Structure 4

260 F8540002 Misc Small Blds Lawn 3

Structure 4

130 F8560001 SAS Bld Exterior 3

Structure 1

179 F8560002 SAS Bld Interior 3

Structure 1

164 F8570001 Sub-Surface Vaults 3

Structure 3

2153 Area 800000 Tank Farm & RHUT F8100011 Tank Farm Southwest and Steam Sump (surface)

I 1 Soil 5

672 F8100012 I Tank Farm Southwest and Steam Sump (subsurface) 1 Soil 1

5 672 10 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8100021 Tank Farm NW Quadrant (surface) 1 Soil 5

1618 F8100022 Tank Farm NW Quadrant (subsurface) 1 Soil 5

1618 F8100031 Tank Farm NE Quadrant (surface)

.1 Soil 5

1942 F8100032 Tank Farm NE Quadrant (subsurface) 1 Soil 5

1942 F8100041 Tank Farm CST and #2 & #3 Pads I

Structure 5

195.1 F8100042 Tank Farm DRCST Pad 2

Structure 5

177.4 F8100043 Tank Farm BWST Pad 1

Structure 5

187 F8100044 Tank Farm Tritium Evaporator Pad 2

Structure 5

148 F8100051 Tank Farm Trench 1 1

Soil 5

750 F8100052 Tank Farm Trench 1 (surface) 1 Soil 5

660 F8100053 Tank Farm Trench 1 (subsurface) 1 Soil 5

660 F8370001 RHUT and Aux. Boiler Pad (surface) 1 Soil 5

1819 F8370002 Tank Farm/ RHUT (subsurface) 1 Soil 5

1819 Area 800000 Reactor Building F8110111 Rx Building FSS Ring (+75'to +115')

1 Structure 5

1966 F8110112 Rx Building FSS Ring (+25' to +75')

1 Structure 5

1966 F8110113 Rx Building FSS Ring (-27' to +25')

1 Structure 5

1762 F8110114 Rx Building Floor -27' 1

Structure 5

1125.4 F8111571 Reactor Bld Dome I

Structure 1

1941 F8111591 RxBuilding Tendon Gallery 3

Structure 5

1817 F8113000 Rx Building Exterior Dome 3

Structure 5

575 F8113001 Rx Building Exterior 3

Structure 5

5516 11 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 Area 800000 Spent Fuel Building F8120001 Spent Fuel Pool West Wall 1

Structure 5

185.9 F8120002 Spent Fuel Pool South Wall 1

Structure 5

137.7 F8120003 Spent Fuel Pool East Wall 1

Structure 5

206.6 F8120004 Spent Fuel Pool North Wall I

Structure 5

267 F8120005 Spent Fuel Pool Floor 1

Structure 5

175-2 F8120111 Cask Catcher Pad 1

Structure 4

103 F8120121 Spent Fuel Building Exterior 1

Structure 5

122.5 F8120131 Fuel Bid Exterior 2

Structure 4

322 F8120141 Spent Fuel Building Exterior 3

Structure 5

854 F8120151 Fuel Bld Exterior 2

Structure 4

332 F8120161 Fuel Bld Exterior 1

Structure 4

123 F8120171 Spent Fuel Building Styrofoam Gap 2

Structure 5

314 F8120181 Spent Fuel Building Styrofoam Gap 1

Structure 5

50 F8121001 Spent Fuel Building Floor 40' El.

1 Structure 5

272 F8121002 Spent Fuel Building 40' El. Lower Walls, North 1

Structure 5

245 F8121003 Spent Fuel Building 40' El. Lower Walls, South 1

Structure 5

115.8 F8121004 Spent Fuel Building 40' El. Upper Walls, South 2

Structure 5

839.9 F8121005 Spent Fuel Building Control Rod Pit 3

Structure 5

33.4 F8121006 Spent Fuel Building 40' El. Upper Walls, North

.2 Structure 5

446.1 Area 800000 Auxiliary Building and Solidification Pad F8130011 Aux Bld Rm 1 Lower 1

Structure 2

189 F8130021 Aux Bld Rm 1 Upper 1

Structurej 2

306 12 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8130022 Aux. Building -47' El. Room 1, Ceiling 1

Structure 5

95 F8130031 Aux Bid Rm 2 Lower 1

Structure 2

165.3 F8130041 Aux. Building -47' El. Room 2, Upper Walls 1

Structure 5

239.5 F8130042 Aux Bid Rm 2 Upper 1

Structure 2

105 F8130051 Aux Bld Rm 3 Lower 1

Structure 3

141 F8130061 Aux Bld Rm 3 Upper 1

Structure 3

302 F8130071 Aux Bld 02 stairs 3

Structure 4

208 F8130081 Aux Bld 01 stairs 1

Structure 4

217 F8130091 Aux Bld Rms 56,127,138 3

Structure 4

178.1 F8130101 Aux Bld Rm 10 Lower 1

Structure 4

57.4 F8130102 Aux Bid Rm 10 Upper 2

Structure 4

239.4 F8130111 Aux Bld Rm 11 Lower 1

Structure 2

21 F8130112 Aux Bld Rm 11 Upper 2

Structure 2

105 F8130121 Aux Bld Rm 12 Lower 1

Structure 2

39.5 F8130122 Aux Bld Rm 12 Upper 1

Structure 2

63 F8130131 Aux Bld Rm 13 1

Structure 3

68.2 F8130141 Aux Bld Rm 14 1

Structure 3

61.6 F8130151 Aux Bld Rm 15, columns N-R 1

Structure 4

238 F8130161 Aux Bld Rm 15, columns R-T 1

Structure 4

310.1 F8130171 Aux Bid Rm 15, column T and East 1

Structure 4

309.9 F8130181 Aux Bld Rm 16 1

Structure 3

114 F8130191 Aux Bld Rm 17 1

Structure 3

167 F8130201 Aux Bld Rm 18 Lower 1

Structure 1

169 13 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8130211 Aux Bld Rm 18 Upper 2

Structure 1

204 F8130221 Aux Bid Rm 19 Lower I

Structure 2

109 F8130222 Aux Bid Rm 19 Upper 2

Structure 2

175 F8130231 Aux Bid Rm 59 Lower 1

Structure 1

43 F8130232 Aux Bid Rm 59 Upper 2

Structure 1

63 F8130241 Aux Bid Rm 20 Lower 1

Structure 2

122 F8130251 Aux Bid Rm 20 Upper 1

Structure 2

213 F8130261 Aux Bld Rm 21 Lower 1

Structure 1

133 F8130271 Aux Bid Rm 21 Upper 2

Structure 1

184 F8130281 Aux Bid Rm 22 Lower 1

Structure 1

213 F8130291 Aux Bld Rm 22 Upper 2

Structure 1

222 F8130301 Aux Bld Rm 23 Lower I

Structure 2

153 F8130311 Aux Bid Rm 23 Upper 2

Structure 2

198 F8130321 Aux Bld Rm 24 1

Structure 3

153 F8130331 Aux Bld Rm 25 Lower 1

Structure 2

132 F8130341 AuxBld Rm 25 Upper 1

Structure 2

185 F8130351 Aux Bld Rm 26 1

Structure 3

182 F8130361 Aux Bld Rm 27 3

Structure 3

283.9 F8130401 Aux Bid Rms 28-31 1

Structure 1

306 F8130411 Aux Bid Rms 32-35 1

Structure 1

302 F8130421 Aux Bid Rm 36, floor and soil walls 1

Soil 4

144.1 F8130431 Aux Bid Rm 36, N. of column 9.7, walls (above one meter) and ceiling

1.

Structure 4

301.1 F8130441 Aux Bid Rm 36, North and East Walls below -25'9" 1

Structure 4

164.6 14 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8130451 Aux Bid Rm 36, Column 9.7 - 11.7, Walls above one meter - ceilings I

Structure 4

247.3 F8130461 Aux Bid Rm 36, South and West concrete walls below 25'9" 1

Structure 4

159.6 F8130471 Aux Bid Rm 36, column 11.7 - south above -25'7" 1

Structure 4

280.9 F8130481 Aux Bid Rm 37 Lower I

Structure 2

236 F8130491 Aux Bid Rm 37 Upper I

Structure 2

316.5 F8130501 Aux Bid Rm 38 Lower I

Structure 2

243 F8130511 Aux Bid Rm 38 Upper I

Structure 2

308.5 F8130521 Aux Bid Rm 39 Lower 1

Structure 2

236 F8130531 Aux Bld Rm 39 Upper 1

Structure 2

315 F8130541 Aux Bld Rm 40 Lower 1-Structure 2

245 F8130551 Aux Bld Rm 40 Upper 1

Structure 2

316.5 F8130561 Aux Bid Rm 41 Lower 1

Structure 2

236 F8130571 Aux Bld Rm 41 Upper 1

Structure 2

316.5 F8130581 Aux Bld Rm 42 Lower 1

Structure 2

225 F8130591 Aux Bld Rm 42 Upper 1

Structure 2

316 F8130601 Aux Bld Rm 43 Lower 1

Structure 1

162 F8130611 Aux Bid Rm 43 Upper 2

Structure 1

167 F8130621 Aux Bld Rm 44 1

Structure 1

278 F8130631 Aux Bld Rm 45 1

Structure 1

263 F8130641 Aux Bld Rm 46 1

Structure 1

265 F8130651 Aux Bld Rm 47 1

Structure 1

97.5 F8130661 Aux Bid Rm 48 1

Structure 1

60 F8130671 Aux Bid Rm 49 1

Structure 1

25 15 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8130681 Aux Bld Rm 50 Lower 1

Structure 1

66 F8130682 Aux Bid Rm 50 Upper 2

Structure 1

107 F8130691 Aux Bid Rm 51, Columns 10.3 to 9.7, Lower 1

Structure 4

125 F8130701 Aux Bld Rm 51, Columns 10.3 to 9.7, Upper 1

Structure 4

202 F8130711 Aux Bid Rm 51, Columns 9.2 to 9.7, Lower 1

Structure 4

140 F8130721 Aux Bid Rm 51, Columns 9.2 to 9.7, Upper 1

Structure 4

220 F8130731 Aux. Bd Rm 51, North of Column 9.1 1

Structure 5

142 F8130732 Aux Bid Rm 51 and 52 Excavation I

Structure 4

93 F8130741 Aux Bid Rm 52, West of Column N Upper 1

Structure 4

288 F8130751 Aux Bid Rm 52, West of Column N Lower 1

Structure 4

177 F8130761 Aux Bid Rm 52, East of Column N Lower 1

Structure 4

150 F8130771 Aux Bld Rm 52, East of Column N Upper 1

Structure 4

214 F8130781 Aux Bid Rm 53 Lower 1

Structure 1

84 F8130782 Aux Bid Rm 53 Upper 2

Structure 1

141 F8130811 Aux Bld Rms 54,55 3

Structure 2

588 F8130861 Aux Bld Rms 102,103 2

Structure 4

246 F8130862 Aux Bid Rm 106 1

Structure 4

296.5 F8130881 Aux Bld Rm2 104-135 3

Structure 3

4926 F8130931 Aux Bid Rm 107 2

Structure 4

146 F8130941 Aux Bld Rms 109, 110 2

Structure 4

898.3 F8130942 Aux. Building Room 109 1

Structure 5

12 F8130991 Aux Bld Rm 112 1

Structure 3

243 F8131001 Aux Bld Rml111 2

Structure 3

83 16 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8131011 Aux Bid Rm 113 2

Structure 3

155 F8131021 Aux Bld Rm 114 2

Structure 3

242.5 F8131031 Aux Bld Rm 115 2

Structure 3

199 F8131041 Aux Bld Rm 117 West 2

Structure 4

716 F8131051 Aux Bld Rm 117 East 2

Structure 4

566.5 F8131191 Aux Bld Rm 130 2

Structure 2

865 F8131201 Aux Bld Rms 131,222,345 3

Structure 2

436 F8131211 Aux. Bld Rm 132, Class 2 2

Structure

5.

995 F8131212 Aux Bld Rm 32, Class 1 1

Structure 5

12 F8131221 Aux Bid Rm 133, Lower 1

Structure 4

271.1 F8131222 Aux Bid Rm 133, Upper 2

Structure 4

270.9 F8131231 Aux Bld Rm 134 1

Structure 4

260 F8131311 Aux Bid Rm Aux Bid Mezzanine Roof 3

Structure 3

482 F8131341 Aux Bld Rms.202,204 3

Structure 2

766 F8131351 Aux Bld Rm 206 3

Structure 3

294 F8131361 Aux Bld Rm 207 3

Structure 3

842 F8131371 Aux. Building Rooms 208, 211, Lower Walls 1

Structure 5

240 F8131372 Aux. Building Rooms 208, 211, Upper Walls 2

Structure 5

811 F8131381 Aux Bld Rm 209 Upper 1

Structure 4

184 F8131382 Aux Bld Rm 209 Lower 1

Structure 4

312 F8131402 Aux Bld Rm 210 Upper 2

Structure 4

205 F8131 403 Aux Bld Rm 210 Lower 1

Structure 83 F8131411 Aux Bld Rms 212-226,ped 3

Structure 4

4546 17 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8131561 Aux Bld Roof 3

Structure 4

1434 F8131601 Aux Bid Non-Cont Rms 3

Structure 2

6314 F8131691 Aux. Building Rooms 309-317, and 350, Lower Walls 2

Structure 5

716 F8131692 Aux Building Rooms 309-317 and 350, Upper Walls 3

Structure 5

589 F8131781 Aux Bld Rm 319 Lower 1

Structure 4

85 F8131782 Aux Bld Rm 319 Upper 2

Structure 4

132 F8131791 Aux Bld Rms 320 Lower 2

Structure 4

59 F8131792 Aux Bid Rm 320 (all), 321 Upper 3

Structure 4

273 F8131811 Aux Bld Rms 322-324,351 3

Structure 4

853.

F8131812 Aux Bld Rms 322-324,351 3

Structure 4

283 F8132051 Aux Bld Rms 346,elev 3

Structure 4

195.6 F8132131 Aux Bid Exterior 2

Structure 4

310.7 F8132132 Aux. Building Exterior 20' El. Steam Support Structure 2

Structure 5

276.5 F8132133 Aux. Building Exterior 0' El. Steam Support Structure 1

Structure 5

4 F8132134 Aux. Building Exterior 20' El. Steam Support Structure 1

Structure 5

2.25 F8132141 Aux Bid Exterior 3

Structure 4

698.6 F8132142 Aux Bid Ext South Wall 3

Structure 4

426.6 F8132143 Aux. Building Exterior Walls, East 3

Structure 5

410 F8132144 Aux. Building Exterior Walls, North 3

Structure 5

376.8 F8500011 Solidification Pad, NE Lower 1

Structure 2

236 F8500012 Solidification Pad, S Lower I

Structure 2

211 F8500013 Solidification Pad Beneath NE Section I

Structure 2

43 F8500014 Solidification Pad, NW Lower 1

Structure 2

118 18 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 Area 826000 Turbine Building F8260001 Turbine Building, Condenser Pit I

Structure 2

35.8 F8260002 Turbine Building, Polisher Sump 1

Structure 2

22 F8260004 Turbine Building, Condenser Pump Pit, Central 1

Structure 5

286 F8260006 Turbine Building, Condenser Pump Pit, South 1

Structure 5

310 F8260008 Turbine Building, High Pressure Turbine Pit 2

Structure 5

346 F8260010 Turbine Building, Condenser Pump Pit, North 1

Structure 5

319 F8260011 Turbine Building, Lube Oil Pit I

Structure 5

160.4 F8260031 Turbine Sumps Piping 1

Structure 5

2 F8260032 Turbine Building, Main Feed Pump Area 2

Structure 5

186.2 F8260131 Turbine Building, Grade Level, North 2

Structure 5

618.3 F8260141 Turbine Building, Grade Level, South 2

Structure 5

980.5 F8260151 Turbine Building, Grade Level, South 1

Structure 5

16 F8260161 Turbine Building Floor, North 1

Structure 5

11.6 F8260171 Turbine Building, Grade Level, North 1

Structure 5

16.6 F8260201 Turbine Building, Mezzanine, Interior Walls 3

Structure 5

1776 F8260202 Turbine Building, Structural Steel 3

Structure 5

9134.2 F8260251 Turbine Building, North Laydown Area 3

Structure 5

679 F8260261 Turbine Building, South Laydown Area and Sump 3

Structure 5

573.7 F8260302 Turbine Building, Exterior 3

Structure 5

1596 F8260303 Turbine Building Deck 2

Structure 4

815 F8260304 Turbine Building Deck 2

Structure 4

953 F8260305 Turbine Building Deck 2

Structure 4

847 19 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 F8261001 S Turbine Pedestal 3

Structure 2

633.7 F8261002 LP Turbine Pedestal 3

Structure 3

996 F8261003 Turbine Building, Pedestal 1 1

Structure 5

309.8 F8261004 Turbine Building, Pedestal 2 1

Structure 5

262.2 F8261005 Turbine Building, Pedestal 3 2

Structure 5

236.5 Area 600000, 700000, 800000: Railway F8340011 Industrial Area Railway 1

Soil 5

100 F8340012 Industrial Area Railway 2

Soil 5

4735 F8340021 Railway External to the Industrial Area 3

Soil 5

5990.

Area 899000 Embedded Piping F8990021 Aux Feedwater Pipe 3

Piping 2

43.2 F8990071 Turbine Bld Drains East Grade Level 1

Piping 3

11.1 F8990072 Turbine Bld Drains +40 Elevation 1

Piping 3

22.8 F8990073 Turbine Bld Drains Grade Level 1

Piping 3

180 F8990074 High Pressure Turbine Pedestal Drain 1

Piping 5

8 F8990111 Decay Heat Removal System Piping 1

Piping 5

49 F8990401 Reactor Building Drains 1

Piping 5

12.3 F8990421 Radwaste System Piping 1

Piping 4

89 F8990422 East Radwaste System Piping 1

Piping 4

. 30.4 F8990423 West Radwaste System Piping 1

Piping 4

10.7 F8990441 Spent Fuel Pool Piping 1

Piping 5

38 F8990521 Acid Waste Pipe 1

Piping 3

29.6 20 Release of Rancho Seco Land from the 10 CFR Part 50 License Table 1.0 Survey Survey Submittal Survey Unit SUID#

SU Name Class Type Number Size m2 Area 800000 Buried and Excavated Piping F8990054 CDS-Clean Drain Pipe 3

Piping 3

4644 F8990060 Comp Cool Water Pipe 3

Piping 2

37.6 F8990091 CDS-Storm Drains 3

Piping 2

2733.5 F8990098 CDS Cross-Tie 2

Soil 5

91.5 F8990281 Main Condensate Pipe 3

Piping 2

135.7 F8990291 Circulating Water Pipe 3

Piping 3

4515 F8990321 Nitrogen Pipe 2

Piping 3

24.7 F8990351 Nuclear Service Water Pipe 3

Piping 3

35.4 F8990431 Service Air Pipe 3

Piping 2

207 F8990471 Service Water Pipe 3

Piping 3

250.3 F8990501 Waste Gas Pipe 3

Piping 2

24.1 F8990511 Carbon Dioxide Pipe 2

Piping 3

2.5 F8991071 CDS-Oily Water Separator 3

Piping 2

115.2 F8991072 CDS-Oily Water Separator, Storm Drains 3

Piping 2

764.9 F8991073 CDS-Oily Water Separator, Transformer Yard Drain Line Trench 3

Soil 3

55 F8991091 RHUT Trench 2

Soil 3

1544 F8991092 CDS-RHUT Pipe 1

Piping 2

187 F8991093 RHUT 8" Drain Lines 2

Soil 5

110 21 Release of Rancho Seco Land from the 10 CFR Part 50 License The soil survey units associated with Survey Areas 100000 through 800000 have been previously noted. Survey units associated with Survey Area 800000 as subdivided in Table 1.0 are described below. The descriptions, HSA history, characterization data and FSS survey results for each individual survey unit noted in Table 1.0 may be found in the submitted FSS Summary Report.

Area ID #: 800000 Survey Area: Miscellaneous Site Structures The Survey Area covers the miscellaneous structures in the Industrial Area. Principle structures include the Administration, Training and Records, NESB, PAP, Diesel Generator, Warehouses, Machine Shop Buildings and the East and West Cooling Tower Basins. The survey units for the region comprise approximately 113,179 M2. Operating records and the HSA history for the individual survey units is provided inthe FSS Summary Reports.

Area ID #: 800000 Survey Area: Tank Farm (810000) and RHUT (837000) Soil and Structures The Survey Area consists primarily of the surface and subsurface soils associated with the Tank Farm, RHUT and Auxiliary Boiler Pad. The structures sited are the remaining concrete pads for the Auxiliary Boiler, Tritium Evaporator, BWST, DRCST and CST.

The survey units for the region comprise approximately 14,880 m 2 which includes the subsurface soil survey units. Operating records and the HSA history for the individual survey units is provided in the FSS Summary Reports.

Area 1ID# : 800000 Survey Area: Reactor Building (811000)

The Survey Area consists of the interior and exterior of the Reactor Building. The survey units for the structure comprise approximately 16,668 in2 which includes the Tendon Gallery survey unit.. Operating records and the HSA history for the individual survey units is provided in the FSS Summary Reports.

Area ID #: 800000 Survey Area: Spent Fuel Building (812000)

The Survey Area consists of the interior and exterior of the Spent Fuel Building. The survey units for the structure comprise approximately 5,145 in2 which includes the gap region between the Spent Fuel Building and The North Diesel Generator Room.

Operating records and the HSA history for the individual survey units is provided in the FSS Summary Reports.

22 Release of Rancho Seco Land from the 10 CFR Part 50 License Area ID #: 800000 Survey Area: Auxiliary Building (813000) and Solidification Pad (850000)

The Survey Area consists of the interior and exterior of the Auxiliary Building and the Solidification Pad. The survey units for the structures comprise approximately 51,000 m2 which includes the interior floors, walls and ceiling as well as the exterior walls and roof surfaces. Operating records and the HSA history for the individual survey units is provided in the FSS Summary Reports.

Area ID #: 800000 Survey Area: Turbine Building (826000)

The Survey Area consists of the interior and exterior of the Turbine Building, the Mezzanine and the Structural Support Steel. The survey units for the structures comprise approximately 22,123 m2 which includes the interior floors, walls and ceiling as well as the exterior walls. Operating records and the HSA history for the individual survey units is provided in the FSS Summary Reports.

Area ID #: 600000. 700000, 800000 Survey Area: Railway (834000)

The Survey Area consist of the Railway survey units in Survey Area 800000 ending at the Industrial Area fence line and the survey unit from the Industrial Area fence line that transverses through Survey Areas 600000 and 700000 terminating at the SMUD property line. These survey units include approximately 10,825 m2 and include the rail region and roadbed on either side of the rails. Operating records and the HSA history for the individual survey units is provided in the FSS Summary Reports.

Area ID #: 800000 Survey Area: Embedded Piping (899000)

The Survey Area consist of the embedded piping survey units associated with Turbine, Auxiliary, Fuel and Reactor Buildings. The associated survey units consist of approximately 524 in 2. Operating records and the HSA history for the individual survey units is provided in the FSS Summary Reports.

Area ID #: 800000 Survey Area: Buried and Excavated Piping (899000)

The Survey Area consists of the buried and excavated piping survey units in the 2

Industrial Area. The associated survey units include approximately 15,477 m. Operating records and the HSA history for the individual survey units is provided in the FSS Summary Reports.

23

Attachment I Release of Rancho Seco Land from the 10 CFR Part 50 License The NRC has reviewed four previous FSS report submittals' for the areas to be released and determined that the FSS reports are acceptable. The NRC documented their review and acceptance of the FSS reports in letters dated April 4, 2008, July 29, 2008, September 23, 2008 and April 23, 2009. A fifth and final FSS report submittal is currently being reviewed by the NRC.

Survey areas for the remaining portion of the licensed site (i.e., the fenced-in area surrounding the IOSB) will be addressed when the IOSB is decommissioning and will remain under the 10 CFR Part 50 license until FSS reports for those areas are completed and the NRC terminates the Rancho Seco Part 50 license.

2.2 Remaining Decommissioning Activities SMUD has completed all decommissioning and dismantlement activities for the first phase of Rancho Seco decommissioning. Accordingly, no further dismantlement activities are required in the survey areas to be released from the license. The FSS Reports for each of the survey areas to be released have been submitted to the NRC previously, as listed in Table 1 of the transmittal letter.

The Class B and C radioactive waste remains stored in the IOSB. SMUD will complete the final phase of decommissioning when a suitable disposal facility becomes available. The remaining activities for the final phase of decommissioning include shipment of all remaining radioactive waste followed by an expectedly minimal decontamination of the structure surfaces in the storage area. The spent nuclear fuel and Greater than Class C (GTCC) waste will remain stored at the ISFSI under 10 CFR Part 72.

2.3 Controls to Prevent Recontamination The Class B and C radioactive waste remains stored in the IOSB. The IOSB is a passive storage facility since no additional radioactive waste will be generated during the storage period.

The contamination controls to be implemented in the IOSB during the second phase of decommissioning are similar to those implemented during the first phase of decommissioning. Examples of controls to be implemented to ensure no recontamination may include:

0 Personnel training

° Installation of barriers to control access to surveyed areas 1 See SMUD letters MPD&C 07-089 dated November 19, 2007, MPC&D 08-008 dated January 24, 2008, MPC&D 08-032 dated May 14, 2008, and MPC&D 08-064 dated July 31, 2008.

24 Release of Rancho Seco Land from the 10 CFR Part 50 License Installation of postings requiring individuals to perform contamination monitoring prior to accessing surveyed areas

• Locked entrances to surveyed areas of the facility

• Periodic routine Radiation Protection surveys to ensure no re-contamination occurs. If recontamination is identified, an investigation will be initiated in accordance with the site corrective action program.

All of the spent nuclear fuel and Greater than Class C (GTCC) radioactive waste are stored at the Rancho Seco ISFSI, in a NUHOMS horizontal storage system, which is licensed under 10 CFR Part 72. The NUHOMS canisters have double closure seal welds to form a pressure retaining confinement boundary and to maintain a helium (i.e., non-oxidizing) atmosphere. Consequently, there is no release of radioactive material during normal conditions of storage.

Chapter 8 of the Rancho Seco ISFSI Final Safety Analysis Report (FSAR) provides engineering analysis for normal, off-normal, and accident conditions. The analysis in Chapter 8 shows that there is no credible event that would lead to a breach of a canister.

Consequently, there are no normal, off-normal, or accident conditions that would result in the release of radioactive material to areas that have been released for unrestricted use.

2.4 Impact of Proposed Site Release on Programs and Documents 2.4.1 Defueled Safety Analysis Report (DSAR)

The proposed release will require changes to the DSAR to describe the site area resulting from the removal of the subject survey areas from the 10 CFR Part 50 license. DSAR Figure 2-2.will be revised to identify the new site boundary.

2.4.2 Technical Specifications The Rancho Seco Technical Specifications do not include a description of the site. Accordingly, the Technical Specifications are not affected by the release of the of the subject survey areas.

The 10 CFR Part 72 ISFSI Technical Specifications are also not affected.

2.4.3 Radiological Environmental Monitoring Program (REMP)

Solid, liquid, and gaseous radioactive waste systems that supported plant operations have been removed and disposed of. The first phase of decommissioning has been completed and liquid and gaseous discharges 25 Release of Rancho Seco Land from the 10 CFR Part 50 License are no longer made from the reactor building, auxiliary building, or spent fuel building.

Some radioactive waste will continue to be stored in the IOSB until a suitable disposal facility becomes available. Accordingly, the REMP has been revised to reflect direct radiation monitoring for the IOSB and the ISFSI.

2.4.4 Offsite Dose Calculation Manual (ODCM)

Solid, liquid, and gaseous radioactive waste systems that supported plant operations have been removed and disposed of. The first phase of decommissioning has been completed and liquid and gaseous discharges are no longer made from the reactor building, auxiliary building, or spent fuel building. Miscellaneous gaseous discharges may continue through the IOSB stack. Accordingly, the ODCM was revised to reflect that Rancho Seco no longer performs liquid effluent discharges.

2.4.5 Emergency Plan The emergency plan has been revised to reflect that Rancho Seco no longer performs liquid effluent discharges. The emergency plan addresses the IOSB and ISFSI. The emergency plan is not affected by the release of the of the subject survey areas.

2.4.6 Security Plan The security plan applies to the 10 CFR Part 72 licensed ISFSI only and is not affected by the release of the proposed areas.

2.4.7 License Termination Plan (LTP)

The requested release is consistent with the LTP. The proposed release does not impact the LTP.

2.4.8 Groundwater Due to the depth of the water table there is no groundwater monitoring program at Rancho Seco.

2.4.9 10 CFR Part 100 Siting Criteria 10 CFR Part 100 addresses design and environmental aspects to be considered when siting a power reactor. Decommissioning the power 26 Release of Rancho Seco Land from the 10 CFR Part 50 License reactor portion of the site has been completed. Only the ISFSI and IOSB will remain after the requested release. Therefore, the criteria in 10 CFR Part 100 no longer applies to this site and do not need to be addressed.

2.4.10 Decommissioning Environmental Report Rancho Seco staff evaluated the environmental impacts of decommissioning Rancho Seco, as documented in the Rancho Seco Environmental Report -

Post Operating License Stage. This report compared Rancho Seco decommissioning attributes to those identified in NUREG-0586 "Final Generic Environmental Impact Statement on decommissioning of nuclear facilities" (GEIS). The assessment determined that the environmental effects for decommissioning of Rancho Seco are minimal, and there are no adverse effects outside the bounds of NUREG-0586.

The phased release of the Rancho Seco site is discussed in the LTP and the requested release is consistent with the process in the LTP. Therefore, the Rancho Seco Environmental Report - Post Operating License Stage and the conclusions in LTP Chapter 8 are not impacted by the requested release.

2.5 NRC Inspections and Confirmatory Surveys NRC contractors from the Oak Ridge Institute for Science and Education (ORISE) performed multiple confirmatory radiation surveys and sample analysis to independently assess the radiological conditions at the site. Samples were tested by gamma spectroscopy for Co-60, Cs-137, and other gamma emitting radionuclides associated with the Rancho Seco site. Reports of ORISE and NRC surveys and sample analysis are public records and verify the Final Status Survey program implemented at Rancho Seco.

3.0 Conclusions The NRC's review of the Rancho Seco LTP determined that the proposed DCGLs would ensure that the 10 CFR 20, Subpart E release criteria would be met. The final status survey (FSS) reports are consistent with, and demonstrate compliance with, the LTP. The FSS results demonstrate that the survey areas to be released meet the radiological criteria for unrestricted release.

NRC inspections and confirmatory measurements verified that the decommissioning and FSS programs adequately addressed the radiological conditions at the Rancho Seco site. Accordingly, the NRC should approve the request to release the subject survey areas form the Rancho Seco 10 CFR Part 50 license.

27 Post FSS Particle Surveys at Rancho Seco

Background

During ORISE confirmatory surveys in December 2007, two instances of small (particle-like) sources of activity were discovered, one inside the Auxiliary Building, one in the Class 1 RHUT Land Area. Based on these discoveries, SMUD instituted a series of preventative actions, including increased monitoring of border areas between Survey Units that had completed FSS adjacent to Survey Units still "in service". Increased contamination controls were also imposed specifically inside of the buildings. In addition, SMUD developed a "particle scan" protocol based on the ability to detect a 1 uCi Co-60 particle. These actions and the new survey basis were found acceptable by the NRC.

Particle Scan Basis SMUD's approved LTP implements the approved survey guidance found in MARSSIM. This uses an approach that combines statistical analysis of samples along with scans of survey units in order to determine the dose consequence of the residual radioactivity remaining in the survey unit. MARSSIM assumes that the residual radioactivity has some spatial distribution, i.e., that the residual radioactivity is distributed over a region and is not contained in a relatively small location like a particle. After the ORISE discoveries in December 2007, the survey protocols were revised to allow detection of particles as well as satisfy the MARSSIM survey protocols.

The particle surveys consist of surveying using a 2 X 2 Nal detector in the same MARSSIM fashion (i.e., "z"-pattern over a designated area) but using a scan speed 50% slower than the scan speed for MARSSIM surveys. Note that the "z"-pattem also is based upon a "region" of detection and does not cause the detector to reside directly over every square inch of the survey unit. However, with the reduced scan speed, the technical bases (and all subsequent surveys) demonstrate SMUD's ability to detect a 1.0 uCi Co-60 particle. As illustrated below, the 100 cm length of the idealized 1.0 m2 survey area is divided into five 20 cm wide nodes. The detector is moved diagonally from the bottom left corner of one node to the top right corner of the next node and then to the top left comer of the next node until the region length is completed. The detector is moved at a fixed speed, for discrete particles the speed used was 0.25 m/s which is one-half the speed recommended by MARSSIM. The maximum node to particle surface location is 20 cm. If the particle is 15 cm deep the distance is 25 cm.

28 Post FSS Particle Surveys at Rancho Seco Consequence of a I uCi Co-60 Particle In the absence of general guidance for determining the dose consequence of a particle, SMUD used NRC-recommended protocols and implemented one of two different methods for determining the dose consequence of particles based upon its location on a structural surface (i.e., inside a building) or in soils. For soils, the dose consequence can be determined by examining the total particulate activity as if it were distributed over a 1.0 m2 area, 15 cm deep and comparing this result to the DCGL. For building surfaces, it was suggested that the "George Xu" published paper be used as the basis. The consequences of each are shown in the Tables below and show that in no case is the 10 CFR 20 criteria for license termination exceeded, demonstrating that a detection limit of 1.0 uCi Co-60 provides reasonable assurance that an undetected particle less than 1.0 uCi will not result in exceeding the release criteria.

Table 1.0 Distributed Source Concentration Distributed Source Area (1.0 m2)a Activity pCi/g 1.0 4.17

'Volume Assumed: 1.0 m2 0.15 cm deep -1.50E+05 cm3 and p = 1.6 g/cm3 V

• p = 2.40E+05 g Table 2.0 Discrete Particle Skin Dose (EDE) 1.0 uCi Co-60 Discrete Particle EDE urem/h/uCi 48.631 EDE urem (8.0 hrs)a 389.0 EDE urem/y.

389.0

'8.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> is the time assumed that a particle is in contact before discovery and removal or, when the particle is rermoved from the skin during showering actions at the end of a work day.

bX.G. Xu, Health Physics 89 (1):53-70; 2005 29 Post FSS Particle Surveys at Rancho Seco Post-FSS non-MARSSIM Survey Protocol During ORISE confirmatory surveys in December 2008, a particle was discovered in the Reactor Building emergency sump. The particle was collected into a vacuum and was not able to be analyzed to determine the exact quantity of radioactivity in the particle, but based upon similar particles and the survey results a reasonable estimate was made with the result being well below 1.0 uCi Co-60. During ORISE confirmatory surveys in March 2009, three additional "particles" were discovered (some were rocks several grams in mass). In no case were the particles above the 1.0 uCi threshold. However, even though the residual radioactivity discovered was well below any "limit", SMvUD agreed to perform additional surveys of the Class 1 land areas adjacent to the power block as well as the routes used for transporting radioactive waste during the decommissioning process. A protocol was instituted to emulate the ORISE surveys, where the focus was not on a regimented MARSSIM-type survey pattern designed to detect regions of contamination that are large in relation to the detector size, but was instead based upon finding and detecting areas of contamination very small in relation to the size of the detector. These surveys were conducted under "ideal" conditions with essentially zero site activity occurring during the surveys: no passing vehicles, no motorized equipment being used anywhere near the surveys, no work being conducted in the vicinity, etc. The focus was on finding and locating any activity above background, not the MARSSIM technical basis of detecting a small fraction of a DCGL. The map in Figure 1.0 below presents the areas surveyed using this protocol.

Post-MARSSIM Survey Results Many instances of particle-like activity were detected, as summarized in Table 3.0 below. These ranged in physical size from true sand-grain or smaller "particles" to rocks and/or concrete aggregate with a mass of several grams. In each case the particles were retrieved and analyzed in the lab using HPGe equipment to identify and quantify the radioactivity. No particles approaching or exceeding 1.0 uCi were detected.

30 Post FSS Particle Surveys at Rancho Seco Figure 1.0 31 Post FSS Particle Surveys at Rancho Seco Table 3.0 Survey Results Inventory Location Size Discrete 44-10 HPGe Analysis Results 1.0 m2 Distributed Activity in pCi/g2 Item Description Particle?

cpm' Co-60 Cs-137 Eu-152 Eu-154 Co-60 Cs-137 Eu-152 Eu-154 1

Tank Farm 8100031 concrete -6 g No 42,521 4.66E+03 7.20E+03 4.67E+02 1.92E-02 3.OOE-02 1.95E-03 2

Tank Farm 8100031 "speck" Yes 60,621 1.78E+05 7.42E-01 3

Tank Farm 8100021 concrete chip No 7,753 3.90E+04 1.63E-01 4

Tank Farm 8100011 rock aggregate No 19,000 3.26E+04 1.36E-01 5

Tank Farm 8100011 rock aggregate No 55,000 1.74E+05 7.23E-01 6

Tank Farm 8100021 rock aggregate No 24,000 5.74E+04 2.39E-01 7

Tank Farm 8100021 rock aggregate No 28,000 9.46E+04 3.94E-01 8

Tank Farm 8100021 rock aggregate No 41,000 1.27E+05 5.28E-01 9

Tank Farm 8100021 sand grain Yes 20,000 4.36E+04 1.82E-01 10 Tank Farm 8100021 sand grain Yes 68,000 1.25E+05 5.21E-01 11 Tank Farm 8100021 rock chip No 18,600 4.15E+04 1.73E-01 12 Tank Farm 8100021 rock aggregate No 8,000 2.83E+04 1.18E-01 13 Tank Farm 8100021 rock aggregate No 134,000 2.07E+02 4.38E+05 8.63E-04 1.83E+00 14 Tank Farm 8100021 metal shaving No 60,000 1.1OE+05 4.57E-01, 15 Tank Farm 8100021 rock aggregate No 36,000 1.08E+05 4.49E-01 16 Tank Farm 8100021 rock aggregate No 10,000 1.97E+04 8.19E-02 17 Tank Farm 8100021 rock chip Yes 15,000 2.91E+04 1.21E-01 18 Tank Farm 8100021 rock aggregate No 18,000 6.06E+04 2.53E-01 19 Tank Farm 8100021 rock aggregate No 15,000 3.61E+04 1.50E-01 20 Tank Farm 8100031 sand grain Yes 71,000 L.19E+05 4.97E-01 21 Tank Farm 8100031 rock aggregate No 60,000 8.04E+04 3.35E-01 22 Tank Farm 8100031 sand grain Yes 87,000 1.37E+05 5.69E-01 23 Tank Farm 8100031 rock aggregate No 21,000 4.73E+03 2.05E+04 1.58E+03 1.97E-02 8.53E-02 6.58E-03 24 Trench 1 E. 8100052 rock aggregate No 38,000 1.20E+02 1.12E+05 5.OOE-04 4.67E-01 25 Trench 1 E. 8100052 rock aggregate 3 No 16,000 1.15E+04 4.79E-02 26 S.E.I.A. 8000091 particle Yes 202,000 3.49E+05 1.45E+00 27 Crtl I.A. 8000106 particle Yes 45,000 8.07E+04 -

3.36E-01 28 Crtl I.A. 8000106 rock aggregate No 46,000 4.94E+01 1.40E+05 2.06E-04 0.585 29 CAl I.A. 8000106 particle Yes 33,000 4.38E+04 1.83E-01 30 C. Twr. Buf 8080031 particle Yes 42,000 6.62E+04 2.76E-01 31 C. Twr. Buf 8080031 particle Yes 83,000 1.47E+05 6.11 E-01 32 C. Twr. Buf 8080033 metal sliver Yes 288,000 7.61E+05 3.17E+00 With the exception of items 1-3 the 44-10 detector measurements represent the count rate of the item after removal from the soil.

Items 1-3 Model 44-10 detector values are one minute static counts over the suspect location prior to removal from the soil.

2Assumes 100 cmx 100 cmx 15 cm depth and density of 1.6g/cm 3=2.40E+05 g 3Nb-94 identified by HPGe analysis 2.241E+02 pCi -9.34E-04 pCi/g: normally associated with in-vessel components composed of Inconel 32 Post FSS Particle Surveys at Rancho Seco Dose Consequences of Discoveries As can be seen, the individual dose consequences of these particles are insignificant. In fact, if all of the activity of these discoveries is distributed in a single area of 1.0 m2 by 15 cm deep, the DCGL is not exceeded. Summing all of the particulate activity results in the following soil values: 9.24 pCi/g, Co-60; 6.59 pCi/g, Cs-137; 0.12 pCi/g, Eu-152 and 8.52E-03 pCi/g, Eu-154. Examining the mixture concentrations using the unity rule where the single nuclide DCGL for Co-60 is 12.6 and the Cs-137 surrogate DCGL for hard-to-detect nuclides is 52.6 pCi/g, the screening levels from NUREG 1757 Volume 2 Revision 1 Table H-2 are used for Eu-152 (8.7 pCi/g) and Eu-154 (8.0 pCi/g), then, 9.24 6.59 0.12 8.52E - 03 =

12.6 60Co 52.6 137surCs 8.7 152Eu 8.0 154Eu

==

Conclusions:==

1. No activity discovered by ORISE or SMUD results in exceeding the 10 CFR 20 license termination criteria.

2. SMUD'has clearly demonstrated that the facility not only meets the 25 mrem/y limit for unrestricted release of the site, but in fact the residual radioactivity has been reduced to a very small fraction of the limit.

3. No discoveries by ORISE or SMUD resulted in detection of activity above agreed-upon limits.

4. The dose consequences of the discoveries do not result in exceeding the 10 CFR 20 limit for license termination.

5. Surveys based on MARSSIM protocols are sufficient to demonstrate compliance with the 10 CFR 20 release criteria.

6. The results of the SMUD surveys (both during and after FSS) indicate our ability to detect levels of particles well below any values that would result in approaching the 10 CFR 20 limit on license termination.

7.

While SMUD retrieved (i.e., remediated) the particles discovered during the Post-FSS surveys, it was not ALARA to do so: SMUD has demonstrated in the approved LTP that remediation below the 25-mrem/y limit is not necessary.

33 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Soil Samples General Final Status Surveys of the Rancho Seco Nuclear Generating Station (RSNGS) comprised 324 survey units. Sixty (60) of theses survey units represented the associated land areas. Table 1.0 presents the survey classes for these land areas.

Table 1.0 Land Survey Units by Class Survey Class Survey Units 1

15 2

17 3

28 Total 60 This evaluation is intended to examine the soil sample analysis results to determine the impact on radionuclide identities, nuclide fractions and any subsequent changes to the DCGL. The original soil characterization for hard-to-detect (HTD) nuclides and DCGL determination was based on analysis of the highest activity samples available.

Examination of the highest activity samples provides for the highest success in identifying HTD radionuclides that may be associated with the sample locations. During the course of decommissioning areas that could potentially contain high concentrations of HTD nuclides are remediated and the associated activities reduced in concentration for all nuclides that are present. The residual radioactivity associated with the observed and HTD nuclides following remediation are conservative relative to the original DCGL.

Evaluation The evaluation of the site soil survey units consisted of examining the reported positive results for Co-60 and Cs-137 for each survey unit in several steps and the results are provided in Table 2.0 of this evaluation..

In the first step the positive sample results for Co-60 and Cs-137 in each survey unit were individually summed. The Co-60 and Cs-137 results are then added together to determine the total activity for all the positive samples in the survey unit. The summed Cs-137 results are divided by the total activity to determine the nuclide fraction for Cs-137 for the positive results and the same operation is performed for Co-60. This resulted in a biased Cs-137 and Co-60 nuclide fraction for the survey unit because of the domineering presents of positive Cs-137 in all the samples. However, the method resulted in a beneficial evaluation feature. The total activity for all the samples is provided and can be compared to the DCGL as a means of evaluating the significance of the residual radioactivity in the survey unit and of the nuclide mixture.

The second step of the process examines the worst case sample nuclide fraction for Cs-137 and Co-60. This step provides a worst case indicator of the nuclide fraction (but is based on a single sample). Additional information could be acquired by averaging only the Cs-137 and Co-60 samples in the survey unit however in 7 of the 9 survey units 34 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Soil Samples exhibiting both Co-60 and Cs-137 only one to four samples resulted for each survey unit contained positive values for both nuclides. In examining the worst case samples several findings were noted and are discussed under the bulleted items below.

• Variations were noted for several samples where the Co-60 nuclide fraction was significantly above the averaged nuclide fraction presented in the DTBD. To investigate this condition the Cs-137 surrogate DCGL was adjusted by varying the nuclide fraction of Cs-137 and Co-60 in the original mix and plotting the change in the Cs-137 surrogate DCGL as the Co-60 fraction increased. While increasing the Co-60 nuclide fraction the Cs-137 nuclide fraction was decreased proportionately. The graph representing the change is provided in Figure 1.0 below. For example, a 10.0 percent increase in the Co-60 nuclide fraction (and subsequent 10 percent decrease in the Cs-137 nuclide fraction) result in a change in the Cs-137 surrogate DCGL from about 51.0 pCi/g to -33.0 pCi/g. Note that the Cs-137 surrogate DCGL when Co-60 is removed from the mixture does not significantly change over the graph range (52.5-52.35 pCi/g). Also, when the mixture is evaluated using the single nuclide DCGL's for Co-60 (12.6 pCi/g) and the Cs-137 surrogate without Co-60. The mixture is then evaluated using the unity rule.

Figure 1.0 Cs-137 surrogate DCGL Change vs. Co-60 Nuclide Fraction Cs-137 Surrogate Change vs Co-60 Nuclide Fraction 60 5 0

" 40 0.i CL 30-10 0

O.OOE+00 5.00E-02 1.001E-01 1.50E-01 2.00E-01 2.50E-01 3.00E-01 Co-60 nuclide fraction

• As per the above information the first sample to exhibit a significant increase in the Co-60 nuclide fraction (0.09) was SU F8100011 where of 20 samples a single positive result was reported. Examining Table 2.0 data the total activity for all the samples resulted in a total activity of 8.89 pCi/g which is significantly lower than the reduced Cs-137 surrogate value of -33.0 pCi/g. Evaluating the results using the single nuclide DCGL for Co-60 and the Cs-137 surrogate value (-52.35 pCi/g on a unity basis will readily result in the SU unit passing.

35 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Soil Samples 0

From Table 2.0 SU F8100051 indicates a worst case single sample with Cs-137 and Co-60 nuclide fraction results of 0.23 and 0.77, respectively. However the total sample activity is 0.579 pCi/g. The total positive activity associated with 67 samples is only 1.95 pCi/g and is insignificant.

0 SU F8480011 shows a worst case sample where the Co-60 nuclide fraction is 0.083. The Cs-137 surrogate DCGL value associated with this fraction of Co-60 is -35 pCi/g and evaluating the individual sample shows that the Cs-137 residual radioactivity associated with this sample is 9.29 pCi/g Cs-137 and 0.178 pCi/g Co-60. Evaluating the sample using the unity rule would result in a unity value of -0.19.

SU F8480012 shows a worst case sample with a nuclide fraction of 0.137 for Co-

60. This would result in a change to the Cs-137 surrogate DCGL value to -27 pCi/g. The individual sample shows that the Cs-137 residual radioactivity associated with this sample is 20.8 pCi/g and is 0.77 of the surrogate DCGL.

Using the unity rule and both Cs-137 and Co-60 the individual sample result is 0.398.

SU F8480018 indicated a worst case sample with the nuclide fraction for Co-60 of 0.71. The total activity associated with this sample for both Cs-137 and Co-60 is 7.17E-01 pCi/g. The positive value associated with 14 samples is 4.75 pCi/g and insignificant.

Conclusion The nuclide fractions and bases for the surrogate DCGL's developed using pre-remediation analysis data remain valid and applicable for use in all post-remediation surveys. Based on the contents of Table 2.0 the following observations were made:

A total of 25 Survey Unit analysis results were sNIDA.

A total of 24 Survey Unit analysis positive results identified only Cs-137.

One Survey Unit was evaluated using the gross beta DCGL.

Ten Survey Units (16.7%) displayed analysis results for both Co-60 and Cs-137.

Of 1,169 samples for all survey units only 31 samples contained Co-60 (2.7%)

Based on the evaluations performed for the survey units containing both Co-60 and Cs-137 any change in the nuclide fraction did not affect the FSS evaluation.

36 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Soil Samples Survey Units containing positive results for both Cs-137 and Co-60 were evaluated using the Cs-137 surrogate value of 52.6 and the single nuclide DCGL 12.6 Explanation of Table 2.0 Columns Column 1 - Item The item number as the next sequential entry.

Column 2 - Area The physical description or name of a survey unit Column 3 - SUID The Survey Unit Identification Number (the F for final is omitted)

Column 4 -- Class Notes the Survey Unit Class (1, 2 or 3)

Column 5 - Submittal The NRC report (submittal) grouping in which the Survey Unit was submitted (1-5)

Column 6 - Cs-137 (activity in pCi/g)

The activity for the positive Cs-137 results Column 7 - Co-60 (activity in ftCi/g)

The activity for the positive Co-60 results Column 8 - Total activity (activity in XCi/g)

The sum of columns 5, 6 and 7 Column 9 - Cs-137 nf Cs-137 nuclide fraction, Column 6 divided by Column 8.

Column 10 - Co-60 nf Co-60 nuclide fraction, Column 7 divided by Column 8 Column 11 - Cs-137 nf (worst case sample)

The Cs-137 nuclide fraction for the worst case sample Column 12 - Co-60 nf (worst case sample)

The Co-60 nuclide fraction for the worst case sample 37 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Soil Samples Column 13 - Remarks Notes if the data is based on gross beta activity or ýADA where the gamma spectroscopy results are all MDA. If the cell is blank it indicates positive gamma spectroscopy results for Co-60, Cs-137 or both.

Column 14 - Co-60 (Positive Results)

Notes the number of Co-60 positive gamma spectroscopy results.

Column 15 - Cs-137 (Positive Results)

Notes the number of Cs-137 positive gamma spectroscopy results.

Column 16 - Sample Total Notes the total number of gamma spectroscopy samples acquired for the survey unit.

38 Evaluation of Co-60 and Cs-13 7 Nuclide Fraction in FSS Soil Samples Table 2.0 Summary of Nuclide Fractions for All Land Survey Units Positive Activity in pCi/g Total Average Samples Worst Case Sample Results Sample Co-60 Co-Cs-Item Area SUID Class Submittal Cs-137 Co-60 Activity Cs-137 nf nf Cs-137 nf Co-60 nf Remarks 60 137 Total I

Effluent Corridor 1000001 2

3 4.13E-05 3.59E-07 4.17E-05 9.91E-01 8.62E-03 9.89E-01 1.13E-02 2

15 19 2

Effluent Corridor 1000002 2

3 1.13E-05 1.13E-05 1.OOE+00 0.00E+00 0

6 17 3

Effluent Corridor 1000003 2

3 2.88E-05 1.9213-07 2.90E-05 9.93E-01 6.62E-03 9.83E-01 8.46E-03 1

21 21 4

Effluent Corridor 1000004 1

3 1.14E-04 6.57E-07 1.15E-04 9.94E-01 5.73E-03 9.89E-01 1.10E-02 4

15 15 5

South Outfall 2000001 3

3 3.62E-06 3.62E-06 1.00E+00 0.OOE+00 0

11 14 6

Upper/Outer Yard Pavement 5010031 3

3

vMDA 0

0 14 7

Hazardous Waste Building Pad 5010032 3

3 D survey 0

0 14 8

Extended Parking Area Soil 5010041 3

3 5.83E-07 5.83E-07 1.0013+00 0.00E+00 0

4 14 9

Extended Parking Area Pavement 5010042 3

3

ýMvDA 0

0 14 10 Access Road 5010051 3

5

!VIDA 0

0 18 11 Helo Pad Area 8000011 3

4 8.58E-06 8.58E-06 I.OOE+00 0.00E+00 0

2 14 12 Central Transit Area 8000041 3

3 sMlDA 0

0 14 13 West Industrial Area 8000071 3

3 1.211E-07 1.21 E-07 1.OOE+00 0.0019+00 0

2 14 14 Industrial Area West (W. of Barrel Farm) 8000072 3

5

4VDA 0

0 14 15 Industrial Area West (North end) 8000073 3

5 5MlDA 0

0 14 16 South East Industrial Area Lands 8000091 3

5 4.1613-07 4.1613-07 1.OOE+00 0.00E+00 0

4 28 17 Industrial Area Central Yard S/P 8000101 3

5 5.0512-07 5.05E-07 1.00E+00 0.0019+00 0'

1 15 18 Industrial Area Central Yard S/P 8000102 3

5 2.53E-08 2.5319-08 1.00E+00 0.00E+00 0

1 14 19 Aux Building-NESB (Pigeon) Alley 8000103 3

4 5vMDA 0

0 14 20 Pump Alley Access Corridor 8000104 1

5

ýv1DA 0

0 14 21 Industrial Area Roadway 8000105 2

5

ývlDA 0

0 15 22 Central IA Roadway 8000106 2

5

-vMDA 0

0 14 23 Industrial Corridor & NA Whse/Fab 8000111 2

5

_MDA 0

0 15 24 Industrial Area Buffer Zone 8000121 3

3 6.1613-08 6.16E-08 1.00E+00 0.00E+00 0

1 15 25 North Industrial Area 8000141 3

3 2.011E-07 2.011E-07 1.00E+00 0.00E+00 0

1 14 26 North Industrial Area 8000142 3

5

!M DA 0

0 14 39 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Soil Samples Table 2.0

_Summary of Nuclide Fractions for All Land Survey Units Positive Activity in jCi/g Total Averaged Samples Worst Case Sample Results Sample Co-60 Co-Cs-Item Area SUID Class Submittal Cs-137 Co-60 Activity Cs-137 nf nf Cs-137 nf Co-60 nf Remarks 60 137 Total 27 Cooling Tower Buffer South 8080031 2

5

aM DA 0

0 20 28 Cooling Tower Buffer West 8080032 2

5 aIDA 0

0 14 29 Cooling Tower Buffer East 8080033 2

5

!AIDA 0

0 16 30 Sewer Plant Asphalt 8090011 3

2

!v1DA 0

0 14 31 Tank Farm SW & Steam Sump 8100011 1

5 8.74E-06 1.51 E-07 8.89E-06 9.83E-01 1.70E-02 9.10E-01 9.04E-02 1

18 20 32 Tank Farm SW & Steam Sump 8100012 1

5 4.22E-06 4.22E-06 l.OOE+00 0.OOE+00 0

12 40 33 Tank Farm NW Quadrant 8100021 1

5 5.00E-06 5.OOE-06 1.OOE+00 0.OOE+00 0

14 17 34 Tank Farm NW Quadrant 8100022 1

5 3.83E-05 3.65E-07 3.87E-05 9.91E-01 9.44E-03 9.90E-01 9.98E-03 1

7 34 35 Tank Farm Quadrant (surface) 8100031 1

5 7.73E-06 7.73E-06 I.OOE+00 0.OOE+00 0

18 22 36 Tank Farm NE Quadrant (subsurface) 8100032 1

5 6.26E-08 6.26E-08 1.001E+00 0.00E+00 0

1 43 37 Tank Farm Trench 1 8100051 3

5 6.18E-07.

1.33E-06 1.95E-06 3.17E-01 6.83E-01 2.30E-01 7.70E-01 3

2 67 38 Tank Farm Trench 1 surface 8100052 1

5 6.40E-06 6.40E-06 1.OOE+00 0.00E+00 0

17 38 39 Tank Farm Trench I Subsurface 8100053 2

5 7.45E-08 7.45E-08 1.00E+00 0.OOE+00 0

1 28 40 Diesel Fuel Oil Tank Pad Area 8320001 3

3 3.84E-08 3.84E-08 1.00E+00 0.OOE+00 0

1 14 41 Industrial Area Railway 8340011 1

5

ýv1DA 0

0 16 42 Industrial Area Railway 8340012 2

5

ýM1DA 0

0 23 43 Railway External to the Industrial Area 8340021 3

5

!1DA 0

0 16 44 RHUT & Aux Boiler Pad 8370001 1

5

!AMDA 0

0

.18 45 Tank Farm/RHUT Subsurface soil 8370002 1

5

ýM DA 0

0 30 46 Transformer Yard 8390001 3

3 3.58E-07 3.58E-07 1.OOE+00 0.OOE+00 0

0 14 47 Barrel Farm Soil 8430011 1

3 1.39E-07 1.39E-07 1.OOE+00 0.OOE+00 0

1 16 48 Barrel Farm Berm 8430021 2

3 9.90E-08 9.90E-08 1.OOE+00 0.OOE+00 0

2 15 49 North Retention Basin 8480011 1

3 5.36E-05 1.34E-06 5.49E-05 9.76E-01 2.44E-02 9.17E-01 8.30E-02 8

29 29 50 South Retention Basin 8480012 1

3 5.12E-05 2.11 E-06 5.33E-05 9.60E-01 3.96E-02 8.63E-01 1.37E-01 8

21 21 51 Retention Basin Surface Soil 8480017 3

3 1.68E-07 1.68E-07 1.OOE+00 0.OOE+00 0

3 14 52 Retention Basin Concrete Storage Area 8480018 2

3 4.07E-06 6.76E-07 4.75E-06 8.58E-01 1.42E-01 2.90E-01 7.1OE-01 2

14 14 53 Retention Basin Buffer Zone 8480021 3

3 1.78E-07 1.78E-07 I.OOE+00 0.OOE+00 0

2 14 40 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Soil Samples Table 2.0 Summary of Nuclide Fractions for All Land Survey Units Positive Activity in pCi/g Total Averaged Samples Worst Case Sample Results Sample Co-60 Co-Cs-Item Area SUID Class Submittal Cs-137 Co-60 Activity Cs-137 nf nf Cs-137 nf Co-60 nf Remarks 60 137 Total 54 Switch Yard Soil 8510001 3

3 4.42E-07 4.42E-07 1.00E+00 0.OOE+00 0

7 14 55 Switch Yard Pavement 8510002 2

3

_MDA 0

0 14 Switch Yard South (+Retention Basin 56 Buffer) 8510005 3

5 2.44E-07 2.44E-07 1.00E+00 0.00E+00 0

2 14 57 CDS Cross-Tie 8990098 2

5

!INDA 0

0 14 58 CDS Oily Water Separator 8991073 3

3

ýMDA 0

0 15 59 RHUT Pipe Trench 8991091 2

3 3.96E-06 4.49E-07 4.41E-06 8.98E-01 1.02E-01 1

33 53 60 RRHUT 8' Piping 8991093 2

5 sNMDA 0

0 16 41 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Final Status Surveys of the Rancho Seco Nuclear Generating station (RSNGS) comprised 324 survey units. Two hundred sixty-four (264) of these survey units represented the associated structure surfaces. Table 1.0 presents the survey classes for these surface areas.

Table 1.0 Structure Survey Units by Class Survey Class Survey Units 1

140 2

48 3

76 Total 264 This evaluation is intended to examine the surface sample results to determine the impact on radionuclide identities, nuclide fractions and any subsequent changes to the DCGL at the time of final survey. For structures and surfaces the associated DCGL is based on DTBD 05-015, Rancho Seco Nuclear Generating Station Surface Nuclide Fractions and DCGL. The gross beta DCGL: for surfaces was based on dose (25.0 mrem/y) and resulted in a gross beta DCGL of 4.30E+04 dpm/100 cma. The evaluation of principle radionuclides for structures is based on ISOCS measurements that were acquired as FSS scan surveys. Evaluating the nuclide fraction based on scan data can bias the principle nuclides (Co-60 and Cs-137) fraction nuclide fraction because ISOCS measurements are typically performed using a "count to" value where the MDA values were selected based on a conservative criterion (usuallylOOO-2000 dpm/100 cm 2 for Co-60 and Cs-137, respectively).

Table 2.0 presents the 264 structure and surface survey units broken into Survey Class and categories of Gross Beta, <MDA and Other.

Table 2.0 Structure Survey Unit Groups Survey Class Gross Beta

<MDA Other 1

88 4

48 2

33 8

7 3

61 7

8 Total (264) 182 19 63 The Gross Beta category represents survey units where all FSS scan and direct measurement data were gross beta measurements.

The <MDA category represents survey units where scan or direct data measurements were acquired using gamma spectroscopy methods however, the results were below the minimum detectable activity. Data where the Co-60 and Cs-137 radionuclides are below the MDA value are biased and result in high nuclide fractions for Co-60. Items 205 and 208-210 which represent survey units F8260251 and F8260303-F8260305 illustrate this condition where the MDA nuclide fractions for these four survey units average 0.596 and 0.404 for Co-60 and Cs-137 respectively (See Table 4.0, Summary of Nuclide Fractions 42 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples for Structure Survey Units).

The category designated "Other" represents survey units where gamma spectroscopy measurements were acquired for FSS scan measurements and in some instances direct measurements. Of the 63 survey units associated with this category, thirteen survey units contained positive results for both Co-60 and Cs-137. Table 3.0 presents the nuclide fractions associated with these survey units. Table 4.0 provides additional information regarding these survey units.

Table 3.0 Structure Nuclide Fraction Survey Unit Nuclide Fraction ID Co-60 Cs-137 F8120003 0.003 0.997 F8120004 0.070 0.930 F8120005 0.189 0.811 F8130042 0.225 0.775 F8130421 0.030 0.970 F8130451 0.061 0.939 F8130541 0.056 0.944 F8130631 0.093 0.907 F8130641 0.044 0.956 F8130731 0.047 0.953 F8130732 0.077 0.923 F8130761 0.085 0.915 F8260002 0.033 0.967 Average 0.078 0.922 Table 3.0 nuclide fractions result in averaged nuclide fractions for Co-60 and Cs-137 of 0.078 and 0.922, respectively. These fractions are very similar to the Co-60 and Cs-137 nuclide fraction average presented in DTBD 05-015 for all structure samples (0.108 and 0.892). The average Co -60 and Cs-137 nuclide fraction based on the seven samples submitted for vendor analysis for "Hard-to-Detect" nuclides was 0.0207 and 0.839.

Two survey units in Table 3.0 are indicative of higher nuclide fractions for Co-60. These Survey Units are F8120005 and F8130042. The data used to determine the nuclide fraction for Survey Unit F8120005 is based on a single Co-60 result of 7.32E+02 dpm/1OOcm 2 that was greater than the MDA value. The Cs-137 result is also low (3.15E+03 dpm/1OOcm 2). Survey Unit F8130042 also exhibits a high Co-60 nuclide fraction which like the previous result is due to low activity. There were only two positive Co-60 and four positive Cs-137 results for 15 gamma spectroscopy locations.

To further evaluate the results of Table 3.0 the variation in the Co-60 nuclide fraction was examined on a dose basis using the same conditions as found in DTBD 05-015. The spreadsheet below is used to illustrate the basis.

43 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples DTBD 05-015 mixture mrem/y 7 Sample Dose For Average 43000 mrem/y per Normalized 1 dpm dose dpm/100 cm 2 Nuclide 1.0 dpm/100 cm 2

[*fraction mean nf Times nf detectable Wl Co-60 1.645E-03 2.073E-02 2.073E-02 3.409E-05 1.553E+00 Sr-90 2.066E-04 8.348E-02 8.348E-02 1.725E-05 7.858E-01 Cs-134 1.142E-03 3.293E-04 3.293E-04 3.759E-07 1.713E-02 Cs-137 4.496E-04 8.392E-01 8.392E-01 3.773E-04 1.719E+01 Pu-238 7.310E-03 1.174E-03 8.579E-06 3.909E-01 Pu-239 8.197E-03 3.733E-04 3.060E-06 1.394E-01 Pu-240 8.197E-03 3.732E-04 3.059E-06 1.394E-01 Pu-241 1.374E-04 5.328E-02 7.319E-06 3.335E-01 Am-241c 8.361E-03 1.048E-03 8.761E-06 3.992E-01 sum 1.OOOE+00 total->

2.095E+01 Avg. 0 fraction 9.438E-01 Co-60 nf 5.0% Cs-137 adjusted accordingly mrem/y Dose For 43000 mrem/y per Normalized 1 dpm dose dpm/100 cm2 Nuclide 1.0 dpm/100 cm2 Q fraction mean nf Times nf detectable 0 Co-60 1.645E-03 5.OOOE-02 5.OOOE-02 8.224E-05 3.747E+00 Sr-90 2.066E-04 8.348E-02 8.348E-02 1.725E-05 7.858E-01 Cs-134 1.142E-03 3.293E-04 3.293E-04 3.759E-07 1.713E-02 Cs-137 4.496E-04 8.102E-01 8.102E-01 3.643E-04 1.660E+01 Pu-238 7.310E-03 1.174E-03 8.579E-06 3.909E-01 Pu-239 8.197E-03 3.733E-04 3.060E-06 1.394E-01 Pu-240 8.197E-03 3.732E-04 3.059E-06 1.394E-01 Pu-241 1.374E-04 5.328E-02 7.319E-06 3.335E-01 Am-241c 8.361E-03 1.048E-03 8.761E-06 3.992E-01 sum 1.OOOE+00 total==>

2.255E+01 Avg. 0 fraction 9.440E-01 The spreadsheet titled DTBD 05-015 displays the average normalized nuclide fraction, the mrem/y per 1.0 dpm/100 cm 2 value and in the last column the mrem per year dose based on the 43,000 dpm/100 cm 2 DCGL for each nuclide. The total dose is also noted (20.95 mrem/y for Co-60 nuclide fraction of 0.0207). This is the same value provide in DTBD 05-015 where the standard error of the mean was 2.034. The second section of the spreadsheet is titled, "Co-60 nf 5.0% Cs-137 adjusted accordingly" and represents a change in the nuclide fraction for Co-60 and Cs-137. Where the Co-60 fraction is upwardly adjusted (in this case to 5.0%) the Cs-137 nuclide fraction is downwardly adjusted to maintain the mixture total fraction at 1.0. The Hard-to-Detect nuclide fractions were left unchanged. Note that the total dose for this spreadsheet is 22.55 mremly or and increase of about 7.6% from the original data. This extrapolation process was continued and is used to illustrate the total dose for different nuclide fractions of Co-60 (and subsequently Cs-137). The graph below illustrates the results.

44 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Dose in mremly for Co-60 Nuclide Fraction Changes 29.00 -

.28.00 -

27.00-

-~26.00-___

25.00-E S-24.00-0 23.00 -

22.00 -

21.00 2 0.0 0 0.000 0.020 0.040 0.060 0.080 0.100 0.120 0.140 0.160 0.180 0.200 Co-60 Nuclide Fraction The DTBD results of 20.95 mrem/y are noted at the lower left side of the graph line and the value of 28.0 mrem/y for a Co-60 nuclide fraction of 0.15 (Cs-137 nuclide 'fraction of 0.71) is found at the upper right end of the graph line.

Conclusion Based on the above graph the average nuclide fraction provide in Table 3.0 indicates a dose of about 24.0 mrem/y and is in good agreement with the original findings of DTBD 05-015. The nuclide fractions based on FSS are in reasonable agreement with the original data. Remediation actions typicallyreduce the nuclide concentrations for easy and hard to detect nuclides. The use of the original DTBD nuclide fractions for dose determination is conservative.

For all the structure survey units there was a total of 3,133 gamma spectroscopy locations of which there were 170 positive Co-60 results and 1,545 positive Cs-137 results. The positive results for Co-60 were 5.43 percent of the total and indicative that Cs-137 is the dominant nuclide in the residual radioactivity.

Explanation of Table 4.0 Columns Column 1 - Item The item number as the next sequential entry.

Column 2 - Area The physical description or nam& of a survey unit 45 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Column 3 - SUID The Survey Unit Identification Number (the F for final is omitted)

Column 4 - Submittal The NRC report (submittal) grouping in which the Survey Unit was submitted (1-5)

Column 5 - Cs-137 (activity in dpm/100 cm)

The averaged activity for the positive Cs-137 results Column 6 - Co-60 (activity in dpm/100 cm 2)

The averaged activity for the positive Co-60 results Column 7-Other (activity in dpm/100 cm 2)

The averaged activity for the positive results of other nuclides Column 8 - Total activity (activity in dpm/100 cm)

The sum of columns 5, 6 and 7 Column 9 - Cs-137 nf Cs-137 nuclide fraction, Column 5 divided by Column 8.

Column 10 - Co-60 nf Co-60 nuclide fraction, Column 6 divided by Column 8 Column 11 - Remarks Notes if the data is based on gross beta activity; 5MDA where the gamma spectroscopy results are all MDA, or Other where some of the gamma spectroscopy results are positive values.

Column 12 - Co-60 Notes the number of Co-60 positive gamma spectroscopy results Column 13 - Cs-137 Notes the number of Cs-137 positive gamma spectroscopy results Column 14 - Total # of Samples Notes the total number of gamma spectroscopy samples for the survey unit.

Column 15 - Class Notes the Survey Unit Class (1, 2 or 3) 46 Evaluation of Co-60 and Cs-137 Nuclide Fraction in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in Positive dpm/100 cm 2 Total Averaged Sample nf Results Co-Cs-Remarks C-s Samples class

[tem Area SUID Submittal Cs-137 Co-60 Other Activity Cs-137 Co-60 60 137 1

Receiving Warehouse Exterior 5010011 1

Gross 13 3

2 Receiving Warehouse Interior 5010012 1

Gross 13 3

3 PAP Building Exterior 8040011 1

Gross 13 3

4 PAP Building Interior 8040012 1

Gross 3 3

5 Administration Building Interior 8050011 1

Gross 3 3

6 Administration Building Exterior 8050012 1

Gross 13 3

7 East and West Cooling Towers 8080011 2

ýMDA 0

0 190 3

8 Tank Farm CST, #2 & #3 pads 8100041 5

1.47E+03 Other 0

1 22 1

9 Tank Farm DRCST Pad 8100042 5

Gross 13 2

10 Tank Farm BWST Pad 8100043 5

Gross 13 1

11 Tank Farm H-3 Evaporator Pad 8100044 5

Gross 13 2

12 RX Building FSS Ring (+75 to 115')

8110111 5

2.99E+03 Other 0

146 180 1

13 RX Building FSS Ring (+25 to 75')

8110112 5

2.85E+03 Other 0

165 180 1

14 Rx Building FSS Ring (-27 to +25')

8110113 5

2.06E+03 Other 0

141 180 1

15 Rx Building Floor -27 Elevation 8110114 5

6.69E+02 Other 0

23 24 1

16 Rx Building Floor -27 Elevation (under vessel) 8110114 5

5.80E-01 1.05E+00 8.40E-01 Other 21 79 160 1

17 Reactor Building Dome Interior 8111571 1

1.24E+04 5.93E+03 Other 72 190 1

18 RX Building Tendon Gallery 8111591 5

Gross 13 3

19 RX Building Exterior Dome 8113000 5

Gross P3 3

20 RX Building (CTMT) Exterior 8113001 5

'VIDA 0

0 40 3

21 Fuel Pool West Wall 8120001 5

1.48E+04 Other 0

40 40 1

22 Fuel Pool South Wall 8120002 5

1.14E+04 Other 0

25 27 1

23 Fuel Pool East Wall 8120003 5

6.80E+05 1.76E+03 6.82E+05 9.97E-01 2.58E-03 Other 2

57 57 1

24 Fuel Pool North Wall 8120004 5

9.78E+05 7.36E+04 1.05E+06 9.30E-01 7.OOE-02 Other 16 89 89 1

25 Fuel Pool Floor 8120005 5

3.15E+03 7.34E+02 3.88E+03 8.1 IE-01 1.89E-01 Other 1

54 68 1

26 Cask Catcher Pad 8120111 4

Gross 13 1

27 Fuel Building Exterior 8120121 5

4.77E+03 Other 0

26 58 1

28 Fuel Building West Exterior Wall AM8120131 4

__IDA 0

0 22 2

47 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in Positive Total # of dpm/100 cm1 Total Averaged Sample nf Results Remarks Co-Cs Samples class

[tem Area SUID

• Submittal Cs-137 Co-60 Other Activity Cs-137 Co-60 60 137 29 Spent Fuel Building Exterior 3 8120141 5

1.95E+03 Other 0

15 24 3

30 Fuel Building East Exterior Wall 8120151 4

1.97E+03 Other 0

3 12 2

31 Fuel Building East Exterior Wall 8120161

.4 3.88E+03 Other 1

14 16 1

32 Styrofoam Gap 8120171 5

Gross P3 2

33 Styrofoam Gap 8120181 5

Gross 3 1

34 Spent Fuel Building Floor El. 40' 8121001 5

2.79E+03 Other 0

33 42 1

35 Spent Fuel Building Lower Walls North 8121002 5

9.37E+02 Other 0

7 16 1

36 Spent Fuel Building Lower Walls South 8121003 5

1.03E+03 Other 0

2 9

1 37 Spent Fuel Building Upper Walls South 8121004 5

8.18E+02 Other 0

15 26 2

38 Spent Fuel Building Control Rod (CR) Pit 8121005 5

Gross P3 3

39 Spent Fuel Building Upper Walls North 8121006 5

1.00E+03 Other 0

1 10 2

40 Aux Building Rm I Lower 8130011 2

Gross 13 1.

41 Aux Building Rm I Upper 8130021 2

Gross 3 1

42 Aux Building Rm 1 -47' El. Ceiling 8130022 5

1.34E+03 Other 0

3 11 1

43 Aux Building Rm 2 Lower 8130031 2

Gross 13 1

44 Aux Building Rm 2 -47' El. Upper Walls 8130041 5

Gross 13 1

45 Aux Building Rm 2 Upper 8130042 2

5.01E+03 1.46E+03 6.47E+03 7.75E-01 2.25E-01 Other 2

4 15 1

46 Aux Building Rm 3 Lower 8130051 3

Gross 13 1

47 Aux Building Rm 3 Upper 8130061 3

Gross 13 1

48 Aux Building Rm 2 Stairs 8130071 4

Gross 13 1

49 Aux Building Rm I Stairs 8130081 4

Gross 13 1

50 Aux Building Rms 56,127, 138 8130091 4

Gross3 P 3

51 Aux Building Rm 10 8130101 4

Gross 13 1

52 Aux Building Rm 10 8130102 4

ýM DA 0

0 4

2 53 Aux Building Rm 11 Lower 8130111 2

Gross 13 1

54 Aux Building Rm I1 Upper 8130112 2

Gross 13 2

55 Aux Building Rm 12 Lower 8130121 2

Gross 3 1

56 Aux Building Rm 12 Upper 8130122 2

Gross 13 1

57 Aux Building Rm 13 8130131 3

Gross 13 1

58 Aux Building Rm 14 8130141 3

Gross 13 1

59 Aux Building Rm 15 8130151 4

1.60E+03 Other 0

6 32 1

48 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in Positive Total # of dpm/100 cm2 Total Averaged Sample nf Results Remarks C0-Cs-Samples class Item Area SUID Submittal Cs-137 Co-60 Other Activity Cs-137 Co-60 R-60 137 Samples class 60 Aux Building Rm 15 8130161 4

2.49E+03 Other 0

13 28 1

61 Aux Building Rm 15 8130171 4

1.43E+03 Other 0

8 33 1

62 Aux Building Rm 16 8130181 3

Gross 13 1

63 Aux Building Rm 17 8130191 3

Gross 13 1

64 Aux Building Rm 18 Lower 8130201 1

Gross 131 65 Aux Building Rm 18 Upper 8130211 1

Gross 13 2

66 Aux Building Rm 19 Lower 8130221 2

Gross 13 1

67 Aux Building Rm 19 Upper 8130222 2

Gross 13 2

68 Aux Building Rm 59 Lower 8130231 1

Gross 13 1

69 Aux Building Rm 59 Upper 8130232 1

Gross 13 2

70 Aux Building Rm 20 Lower 8130241 2

Gross 13 1

71 Aux Building Rm 20 Upper 8130251 2

Gross 13 1

72 Aux Building Rm 21 Lower 8130261 1

Gross 131 73 Aux Building Rrn 21 Upper 8130271 1

Gross 13 2

74 Aux Building Rim 22 Lower 8130281 1

Gross 13 1

75 Aux Building Rm 22 Upper 8130291 1

Gross 13 2

76 Aux Building Rm 23 Lower 81.30301 2

Gross 131 77 Aux Building Rm 23 Upper 8130311 2

Gross 13 2

78 Aux Building Rm 24 8130321 3

Gross 13 1

79 Aux Building Rm 25 Lower 8130331 2

Gross 13 1

80 Aux Building Rm 25 Upper 8130341 2

Gross 13 1

81 Aux Building Rm 26 8130351 3

Gross 13 1

82 Aux Building Rm 27 8130361 3

Gross 13 1

83 Aux Building Demin Cubicles 28,29,30, 31 8130401 1

Gross 13 1

84 Aux Building Demin Cubicles 32,33,34,35 8130411 1

Gross 13 1

85 Aux Building Rm 36 8130421 4

7.16E+00 2.22E-01 7.38E+00 9.70E-01 3.01E-02 Other 10 21 21 1

86 Aux Building Rm 36 8130431 4

8.67E+03 Other 0

35 37 1

87 Aux Building Rm 36 8130441 4

Gross 13 1

88 Aux Building Rm 36 8130451 4

2.57E+04 1.68E+03 2.74E+04 9.39E-01 6.14E-02 Other 13 44 44 1

89 Aux Building Rm 36 8130461 4

Gross 13 1

90 Aux Building Rm 36 8130471 4

2.01E+04 Other 4

48 49 1

49 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in Positive dpm/1 00 cm 2 Total Averaged Sample of Results Total # of Co-Cs-Remarks C-s Samples class

[tern Area SUID Submittal Cs-137 Co-60 Other Activity Cs-137 Co-60 60 137 91 Aux Building Rm 37 Lower 8130481 2

Gross P I

92 Aux Building Rm 37 Upper 8130491 2

1.19E+03 Other 0

2 56 1

93 Aux Building Rm 38 Lower 8130501 2

3.67E+03 Other 0

8 14 1

94 Aux Building Rm 38 Upper 8130511 2

1.88E+03 Other 0

14 56 1

95 Aux Building Rm 39 Lower 8130521 2

5.74E+03 Other 2

14 14 1

96 Aux Building Rm 39 Upper 8130531 2

1.67E+03 Other 0

28 56 1

97 Aux Building Rm 40 Lower 8130541 2

2.177E+04 1.29E+03 2.301E+04 9.44E-01 5.60E-02 Other 3

18 18 1

98 Aux Building Rm 40 Upper 8130551 2

3.02E+03 Other 0

53 56 1

99 Aux Building Rm 41 Lower 8130561 2

Gross P I

100 Aux Building Rm 41 Upper 8130571 2

2.06E+03 Other 0

7 42 1

101 Aux Building Rm 42 Lower 8130581 2

Gross P 1

102 Aux Building Rm 42 Upper 8130591 2

1.77E+03 Other 0

15 53 1

103 Aux Building Rm 43 Lower 8130601 1

Gross P 1

104 Aux Building Rm 43 Upper 8130611 1

Gross P 1

105 Aux Building Rm 44 8130621 1

Gross P_

1 106 Aux Building Rm 45 8130631 1

3.63E+03 3.73E+02 4.01E+03 9.07E-01 9.31E-02 Other 1

10 10 1

107 Aux Building Rm 46 8130641 1

3.36E+04 1.54E+03 3.51E+04 9.56E-01 4.38E-02 Other 5

20 20 1

108 Aux Building Rm 47 8130651 1

Gross P 1

109 Aux Building Rm 48 8130661 1

6.05E+03 Other 0

7 7

1 110 Aux Building Rm 49 8130671 1

1.10E+04 Other 0

6 6

1 111 Aux Building Rm 50 Lower 8130681 1

Gross 0 1

112 Aux Building Rm 50 Upper 8130682 1

Gross 3 2

113 Aux Building Rm 51 8130691 4

Gross P3 1

114 Aux Building Rm 51 8130701 4

Gross P.

115 Aux Building Rm 51 8130711 4

Gross1 116 Aux Building Rm 51 8130721 4

ýM DA 0

0 8

1 117 Aux Building Rm 51e 8130731 5

1.12E+05 5.57E+03 1.18E+05 9.53E-01 4.74E-02 Other 2

44 44 1

118 Aux Building Rm 51 8130732 4

7.82E+03 6.52E+02 8.47E+03 9.23E-01 7.70E-02 Other 8

19 19 1

119 Aux Building Rm 52 8130741 4

1.33E+04 Other 0

21 21 1

120 Aux Building Rm 52 8130751 4

1.07E+04 Other 0

14 15 1

121 Aux Building Rm 52 8130761 4

5.68E+04 5.30E+03 6.21E+04 9.15E-01 8.53E-02 Other 1

8 8

1 50 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in Positive dpm/1[ 0 cm2 Total Averaged Sample nf Results Co-Cs-Remarks C-s Samples class Item Area SUID Submittal Cs-137 Co-60 Other Activity Cs-137 Co-60 60 137 122 Aux Building Rm 52 8130771 4

2.30E+04 Other 0

8 8

1 123 Aux Building Rm 53 Lower 8130781 1

Gross 13 1

124 Aux Building Rm 53 Upper 8130782 1

Gross P_

2 125 Aux Building Rms 54,55 8130811 2

Gross P 3

126 Aux Building Rms 102,103 8130861 4

Gross P 2

127 Aux Building Rm 106 8130862 4

Gross 1

128 Aux Building Rms 104-135 8130881 3

Gross P 3

129 Aux Building Rm 107 8130931 4

Gross 13 2

130 Aux Building Rms 109, 110 8130941 4

3.84E+03 Other 0

8 19 2

131 Aux Building Rm 109 8130942 5

Gross P 1

132 Aux Building Rm 112 8130991 3

Gross 1

133 Aux Building Rm 111 8131001 3

Gross 3 2

134 Aux Building Rm 113 8131011 3

• VIDA 0

0 5

2 135 Aux Building Rm 114,136,137 8131021 3

Gross P 1

136 Aux Building Rm 115,203,315 8131031 3

2.211E+02 Other 0

5 6

2 137 Aux Building Rm 117W 8131041 4

MVIDA 0

0 38 2

138 Aux Building Rm 117E 8131051 4

_VIDA 0

0 41 2

139 Aux Building Rm 130 8131191 2

Gross P 2

140 Aux Building Rms 131.222.345 8131201 2

Gross 3 3

141 Aux Building Rm 132 8131211 5

Gross P 2

142 Aux Building Rm 132 8131212 5

Gross 3 1

143 Aux Building Rm 133 8131221 4

Gross P 1

144 Aux Building Rm 133 8131222 4

Gross P 2

145 Aux Building Rm 134 8131231 4

Gross P 1

146 Aux Building Mezzanine Roof 8131311 3

,,IDA 0

0 8

3 147 Aux Building Rms 202,204 8131341 2

Gross P 3

148 Aux Building Rm 206 8131351 3

Gross P 3

149 Aux Building Rm 207 8131361 3

Gross P 3

150 Aux Building Rm 208, 211 Lowers 8131371 5

Gross 13 1

151 Aux Building Rm 208, 211 Uppers 8131372 5

Gross P 2

152 Aux Building Rm 209 8131381 4

MVIDA 5

1 1

51 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in Positive Total # of dpm/100 cm2 Total Averaged Sample nf Results Co-Cs-Itern Area SUID Submittal Cs-137 Co-60 Other Activity Cs-137 Co-60 Remarks 60 137 Samples class 153 Aux Building Rm 209 8131382 4

ýVDA 1

154 Aux Building Rm 210 8131402 4

Gross P3 2

155 Aux Building Rm 210 8131403 4

Gross P 1

156 Aux Building Rms 212-226 fan pedstals 8131411 4

Gross P3 3

157 Aux Building Roof 8131561 4

4vIDA 0

0 42 3

158 Aux Building Non-Controlled Rooms 8131601 2

2.14E+03 Gross P 3

159 Aux Building Rms 309-317, 350 Lowers 8131691 5

Gross P3 2

160 Aux Building Rms 309-317, 350 Uppers 8131692 5

Gross P 3

161 Aux Building Rm 319 8131781 4

Gross P 1

162 Aux Building Rm 319 8131782 4

Gross P 2

163 Aux Building Rm 320 Lower 8131791 4

Gross P 2

164 Aux Building Rm 320 Upper, Rm 321 8131792 4

Gross P3 3

165 Aux Building Rms 322,-324, 351 8131811 4

Gross P3 3

166 Aux Building Rms 322,-324, 351 8131812 4

Gross 13 3

167 Aux Building Rm 346, Elevator 8132051 4

Gross 3 3

168 Aux Building Exterior 8132131 4

Gross P 2

169 Aux Building Exterior 20' El. Steam Sup. St.

8132132 5

Gross P3 2

170 Aux Building Exterior 0'El. Steam Sup. St.

8132133 5

Gross P 1

171 Aux Building Exterior 20' El. Steam Sup. St.

8132134 5

Gross P 1

172 Aux Building Exterior 8132141 4

9.95E+02 Other 0

1 20 3

173 Aux Building Exterior, South Wall 8132142 4

1.011E+03 Other 0

1 9

3 174 Aux Building Exterior Walls East 8132143 5

ýVIDA 0

0 14 3

175 Aux Building Exterior Walls North 8132144 5

VIDA 0

0 6

3 176 T&R Building Exterior 8140002 1

Gross P_

3 177 T & R Breezeway 8140031 5

Gross P 3

178 T& R Building Interior 8140010 1

Gross P 3

179 Nuclear Service Electrical Building Interior 8150011 1

Gross P 3

180 Nuclear Service Electrical Building Exterior 8150021 1

Gross P 3

181 Diesel Generator Building Interior 8170011 1

Gross P 3

182 Diesel Generator Building Exterior 8170021 1

Gross P 3

183 Water Treatment Building Interior 8210001 1

Gross P_

3 52 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in Positive dpm/ 00 cm2 Total Averaged Sample nf Results Total # of Co-Cs-Remarks C-s Samples class

[tem Area SUID Submittal Cs-137 Co-60 Other Activity Cs-137 Co-60 60 137 184 Water Treatment Building Exterior 8210002 1

Gross 03 3

185 Chlorine Building Interior 8220011 1

Gross 13 3

186 Chlorine Building Extrior 8220021 1

Gross 13 3

187 Intake Structure 8230001 3

Gross 13 3

188 Primary Cooling Water (PCW) Intake 8240001 2

Gross 13 2

189 Condenser Pit Sump Excavation 8260001 2

1.45E+03 Other 1

4 9

1 190 Turbine Building Polisher Sump 8260002 2

4.76E+00 1.60E-01 4.92E+00 9.67E-01 3.25E-02 Other 4

10 12 1

191 Turbine Building, Condensate Pump Pit Ctrl 8260004 5

8.30E+01 6.70E+01 1.50E+02 5.53E-01 4.47E-01

!V DA 0

0 3

1 192 Turbine Building, Condensate Pump Pit South 8260006 5

Gross P3 I

193 Turbine Building, West HP Pit 8260008 5

Gross 13 2

194 Turbine Building, Condensate Pump Pit North 8260010 5

Gross 13 1

195 Turbine Building Lube Oil Pit 8260011 5

Gross 13 1

196 Turbine Building, MFP Pit Sump 8260031 5

Gross 13 197 Turbine Building, Main Feed Pump Area 8260032 5

Gross 13 2

198 Turbine Building Grade Level North 8260131 5

2.34E+03 Other 0

33 59 2

199 Turbine Building Grade Level South 8260141 5

1.94E+03 Other 0

14 47 2

200 Turbine Building Grade Level South Class 1 8260151 5

Gross 13 1

201 Turbine Building Grade Level North 8260161 5

Gross 3 1

202 Turbine Building Grade Level North Class 1 8260171 5

Gross 13 1

203 Turbine Building Mezzanine Interior Walls 8260201 5

6.53E+02 Other 0

3 18 3

204 Turbine Building Structural Steel 8260202 5

Gross 13 3

205 Turbine Building North Laydown Area 8260251 5

1.11E+03 7.12E+02 1.82E+03 6.09E-01 3.91E-01

!qv1DA 0

0 6

3 206 Turbine Building South Laydown Area & Sump 8260261 5

8.11 E+02 Other 0

3 17 3

207 Turbine Building Exterior 8260302 5

7.23E+02 Other 0

6 68 3

208 Turbine Building Deck, North 8260303 4

9.19E+02 6.38E+02 1.56E+03 5.90E-01 4.10E-01

ýMIDA 0

0 42 2

209 Turbine Building Deck, Center 8260304 4

8.65E+02 5.76E+02 1.44E+03 6.OOE-01 4.OOE-01 Vl DA 0

0 57 2

210 Turbine Building Deck, South 8260305 4

8.88E+02 627 1.52E+03 5.86E-01 4.14E-01

ýMDA 0

0 22 2

211 Turbine Building S. Turbine Pedestal 8261001 2

1.01E+03 Other 0

2 25 3

212 Turbine Building LP Turbine Pedestal 8261002 3

1.28E+03 Other 0

2 12 3

213 Turbine Building HP Turbine Pedestal 1 8261003 5

1.14E+03 Other 0

18 36 1

214 Turbine Building HP Turbine Pedestal 2 8261004 5

1 Gross P3 I

53 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in dnm/100 cm2 Positive Results

+

+

r Total Other Averaped Samnle nf

-I I-Total # of Samples

" Item Area SUID Submittal Cs-137 Co-60 Activitv Cs-137 ICo-60 I Remarks Co-Cs-60 137 class 215 Turbine Building HP Turbine Pedestal 3 8261005 5

Gross P 2

216 Microwave Building Interior 8310001 1

Gross P3 3

217 Microwave Building Exterior 8310002 1

Gross 13 2

218 Warehouse B Interior 8330001 1

Gross [3 3

219 Warehouse B Exterior 8330002 1

Gross 13 2

220 Warehouse A Interior 8400001 1

Gross 13 3

221 Warehouse A Exterior 8400002 1

Gross 13 3

222 Discharge Boxes/ Manholes 8480013 2

Gross 13 223 Discharge Boxes/ Manholes 8480014 2

Gross 13 224 Discharge Boxes/ Manholes 8480015 2

Gross 13 225 Discharge Boxes/ Manholes 8480016 2

Gross 13 1

226 Solidification Pad 8500011 2

Gross 13 1

227 Solidification Pad 8500012 2

Gross 13 1

228 Solidification Pad 8500013 2

Gross 31 229 Solidification Pad 8500014 2

Gross 13 1

230 Switchyard Building Exterior 8510003 1

Gross 13 3

231 Switchyard Building Interior 8510004 1

Gross 13 3

232 Machine Shop Interior 8520001 1

Gross 13 3

233 Machine Shop Exterior 8520002 1

Gross 13 3

234 Misc Small Buildings (POL) 8540001 4

Gross 13 3

235 Misc Small Buildings (Lawn Maintenance) 8540002 4

Gross 13 3

236 Secondary Alarm Station Building Exterior 8560001 4

Gross 13 3

237 Secondary Alarm Station Building Interior 8560002 4

Gross 13 3

238 Subsurface Vaults 8570001 4

Gross 13 3

239 Aux Feedwater Piping 8990021 4

Gross 13 3

240 CDS Clean Drain Piping 8990054 3

Gross 33 3

241 Component Cooling Water Piping 8990060 2

Gross 33 3

242 CDS Turbine Building Drains 8990071 3

Gross 31 243 CDS Turbine Building Drains 8990072 3

Gross 13 1

244 CDS Turbine Building Drains 8990073 3

Gross 13 1

245 Turbine Building HP Turbine Pedestal Drains 8990074 5

Gross 13 1

54 Evaluation of Co-60 and Cs-137 Nuclide Fractions in FSS Surface Samples Table 4.0 Summary of Nuclide Fractions for Structure Survey Units All activity in Positive Total # o dpm/100 cm 2 Total Averaged Sample nf Results Ca-Cs-Remarks Co*s Samples class tem Area SUID Submittal Cs-137 Co-60 Other Activity Cs-137 Co-60 R

60 137

!46 Clean Drains To Effluent 8990091 2

Gross 13 3

!47 Decay Heat Piping 8990111 5

Gross 13 1

!48 Main Condensate Piping 8990281 2

Gross 13 3

!49 Main Circ Water Piping 8990291 3

Gross 13

• 3

!50 Nitrogen Piping 8990321 3

Gross 13 2

ý51 Nuclear Service Water Piping 8990351 3

Gross 13 3

!52 Rx Drains 8990401 5

Gross 13

!53 Radwaste Piping 8990421 4

Gross 31

!54 Radwaste Piping 8990422 4

Gross 13 1

!55 Radwaste Piping 8990423 4

Gross 13 1

!56 Service Air Piping 8990431 2

Gross 13 3

!57 Spent Fuel Pool Piping 8990441 5

Gross P3 1

58 Service Water Piping 8990471 3

Gross 13 3

59 Waste Gas Piping 8990501 2

Gross P3 3

560 Carbon Dioxide Piping 8990511 3

Gross P3 2

561 Acid Waste Piping 8990521 3

Gross P3 1

!62 CDS Oily Water Separator 8991071 2

Gross P3 3

!63 CDS Oily Water Separator 8991072 2

Gross P3 3

!64 CDS RHUT Piping 8991092 2

Gross 13 1

55