ML20086K769
| ML20086K769 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos, Vallecitos Nuclear Center |
| Issue date: | 03/25/2020 |
| From: | Feyrer M GE Hitachi Nuclear Energy |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| M200045 | |
| Download: ML20086K769 (44) | |
Text
- HITACHI GE Hitachi Nuclear Energy Matt J. Feyrer Site Manager, Vallecitos Nuclear Center 6705 Vallecitos Rd M200045 Sunol, CA 94586 USA March 25, 2020 T 925 918 6018 Matt.feyrer@ge.cm U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001
Subject:
GEH Annual Shutdown Reactor Reports for the Year 2019
Reference:
License DPR-1, Docket 50-18 (VBWR), License DR-10, Docket 50-183 (EVESR), License TR-1, Docket 50-70 (GETR)
Enclosed are the 2020 Annual Reports for the deactivated Reactors (Vallecitos Boiling Water Reactor (VBWR), ESADA-Vallecitos Experimental Superheat Reactor (EVESR),
and the General Electric Test Reactor (GETR)} located at the GE Hitachi, Vallecitos Nuclear Center near Sunol, California.
If there are any questions or additional information required, please contact me at the number above.
Matt Feyrer, Site Manager Vallecitos Nuclear Center Enclo~ures: VBWR Annual Report No. 55, EVESR Annual Report No. 52, and GETR Annual Report No. 61 cc: NRC Region IV Administrator J. Parrott, NRC NMSS MJF 20-001
Enclosures VBWR Annual Report No. 55 EVESR Annual Report No. 52 GETR Annual Report No. 61
- HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California VALLECITOS BOILING WATER REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 55 FOR THE YEAR 2019 LICENSE DPR-1 DOCKET 50-18 MARCH 2020
VBWR Annual Report No. 55 Vallecitos Boiling Water Reactor (Deactivated)
Annual Report No. 55 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWR) in a deactivated status under the authority of Amendment No. 21 to License DPR-1, Docket 50-18, issued Oct 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented, as required by paragraph 5.d.2 of the license.
1.0
SUMMARY
All reactor systems have been removed from the containment except for the reactor vessel.
The water level within the reactor vessel was monitored and has remained essentially constant throughout the report period.
Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review.
2.0 STATUS OF FACILITY In accordance with written procedures, the Facility Manager controls access to the containment building and general systems. The facility continues to be in deactivated status in safe storage condition.
3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low.
Results of the surveys are presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.
An assessment for radionuclide distribution was performed of the shutdown reactors. An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.
Page 1 of 3
VBWR Annual Report No. 55 3.1 GROUND WATER MONITORING WELL Groundwater well MW-9 was installed southwest of the EVESR and VBWR shutdown reactors.
Monitoring Well 9 has two sampling points documented as MW-9S and MW-9D. These wells will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of the shutdown reactors in this area. The installation of these wells is part of the response letter to the NRC, NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules, GEH Response Summary Dated May 31, 2019. Analytical results of groundwater samples collected from the wells during the reporting periods. These wells were sampled quarterly after installation in 2019.
Well W-9S (4S-1E2P1)
Month Gross Alpha Gross Beta Tritium (pCi/L) (pCi/L) (pCi/L)
July 2019 2.81 1.62 0 October 2019 2.31 2.82 176 Annual Average 2.56 2.22 88 Well W-9D (4S-1E2P2)
Month Gross Alpha Gross Beta Tritium (pCi/L) (pCi/L) (pCi/L)
July 2019 5.04 2.29 395 October 2019 4.10 0.75 270 Annual Average 4.57 1.52 333 4.0 ACTIVITIES Routine inspections were conducted during this report period. This included new monthly routines completed from February to December. Additional activities in VBWR included installation of a new automatic sump pump system in the VBWR Basement, and two monitoring wells downgradient of VBWR.
5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The VBWR Facility Manager remains K. P. Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.
Page 2 of 3
VBWR Annual eport No. 55
6.0 CONCLUSION
GE Hitachi Nucl ar Energy concludes that the deactivated VBWR~s being maintained in a safe shutdown condi ion. The inspections, access control, and administratively controlled activities ensure maximu protection for the public health and safety. The procedures will be continued to maintain this high level of protection.
GE Hitachi Nuclear Energy Vallecitos Operations
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Manager Vallecitos Nuclear Center Page 3 of 3
Attachment 1 SURVEYOR (print and sign) REVIEWER NO.
g HITACHI Name and signature on original at GEH Vallecitos Nuclear Center LOCATION DATE:
D-055 06/18/19 VALLECITOS NUCLEAR CENTER TIME:
NUCLEAR SAFETY SURVEY RECORD VBWR Containment 0900 Routine REASON Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item n TOTAL Distance No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Main Floor - General Area <1-5 <1-5 F 2 - Area Over Reactor Vessel <1 <1 F 3
4 Basement - General Area <1 <1 F 5 - Sump 4 4 C 6 - Sump @ 1' <1 <1 1' 7 Reactor Vessel Head Area <1 <1 F 8
9 Top of Fuel Pool <1 <1 F 10 11 Personnel Air Lock <1 <1 F 12 13 Equipment Air Lock <1 <1 F 14 15 Drum on first floor (Sludge) 38 38 C 16 Drum on first floor (Sludge) @ 1' 8 8 1' INSTRUMENT USED Tennelec PRM - 7 CP - 5 RO - 20 PNR - 4 TBM - E - 120 RM - 15 RM - 14 PAC - 1SA LUDLUM-12 SERIAL NUMBER 2972-1 6128 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE AC - 3A (U) 10% PROBE PANCAKE 20%
COMMENTS Smears completed on Tennelec see attachment EFF. 43 - 4 (U) 10% EFF.
Areas smeared are on maps with attachement (4 P (4 P GEO.) GEO.)
NEO 289 (REV. 07/10)
VBWR Main Floor 1
1 11 Reactor Pit 1
2 1
1 12 3 4 1
10 1
13 Machinery 1 32 contact 1 1 Hatch 9@ 30cm 55-GAL Drum 6 5 1
1 9
Steam Generator 1 Hatch 7
Personal Hatch 8
Equipment Hatch 1 # = Dose Rate
- = Smear Location Dose Rates in mR/hr
VBWR Basement Area 3
4 Reactor Head Diamond Plate 5
1 Reac Slanted Wall tor H ead 2
2 5 contact l
1 1 Leve 3 @ 30cm Sump 7
i 1 5 3 Grat ng Slanted Wall 8 Slanted Wall 6 1 1 1 1
4 1 Ladder To Basement Ladder To Main Floor Slanted Wall Slanted Wall
- = Dose Rate
- = Smear Location Dose Rates in mR/hr
Attachment to Survey D055: VBWR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument: Tennelec XLB System A Analyzed By:
Serial No.: 29722 Signature:
Calibration Date: 1 Mar 2019 Reviewed:
Beta Efficiency: 33.47% Beta MDA: 16.9 dpm Alpha Efficiency: 36.28% Alpha MDA: 10.5 dpm Sample Date: 6/18/19 Count Date: 6/18/19 Alpha Alpha Beta Beta Level Location (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm ) (DPM/100 cm2) 2 2 2 1 0 0 108.2 323 2 0 0 47.2 141 3 0 0 44.2 132 4 0 0 79.2 237 5 0 0 43.2 129 Main 6 0 0 49.2 147 Floor 7 0.9 2.5 33.2 99.2 Level 1 8 0 0 37.2 111 9 0 0 24.2 72.3 10 0.9 2.5 27.2 81.3 11 0 0 89.2 266 12 0 0 51.2 153 13 0 0 28.2 84.2 1 0.9 2.5 95.2 284 2 0 0 28.2 84.2 Rx Head 3 0 0 23.2 69.3 Level 4 (Bricks) 0 0 23.2 69.3 5 (Diamond Plate) 0.9 2.5 104.2 311 1 2.9 8.0 1944.2 5810 2 0 0 579.2 1730 3 0 0 701.2 2090 4 0 0 532.2 1590 Basement 5 0 0 691.2 2060 6 2.9 8.0 738.2 2210 7 (Sump Cover) 0 0 399.2 1190 8 (By Sump) 1.9 5.2 915..2 2730 Page 1 of 1
VBWR & EVESR SITE MAP 7 Mockup Equipment 8
Mockup 7
Equipment Concrete Pad EVESR
Background
1 Soil Sample 9 Mockup Area 8
10 EVESR 3 Soil Sample 9
8 Concrete Ring 11 9
8 8 Building Concrete Pad Cask Cask Cask 11 Concrete Pad EVESR 12 4 Soil Sample 8
12 Cask Cask al 10 son Per tch Ha Cask 14 EVESR Concrete Pad Ve n
12 io at il it nt Un 13 EVESR Equipment Hatch Stack 18 5 Soil Sample 6 VBWR
Background
Soil Sample 1 16 d
e 12 20 22 Building EVESR Tank Pad 6 Soil Sample 30 5 VBWR Soil Sample Personal 32 Hatch 15 56 68 VBWR Equ ip VBWR Ha ment 4 Soil Sample tch VBWR 60 118 90
Background
Soil Sample 3 1000 VBWR
Background
Soil Sample 425 2 80 6 VBWR Soil Sample 410
- = Dose Rate 180
- = Soil Sample Location Dose Rates in microRem/hr
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial 1 Hour Decay >24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E10 792.30 3.77E10 103.39 4.53E11 233.50 1.11E10 0.00 0.00E+00 7.00 3.33E12 Basement 2.83E+06 820.19 3.60E10 1991.90 9.47E10 260.29 1.14E10 592.20 2.81E10 0.49 2.15E13 21.50 1.02E11 Fuel Pool 2.83E+06 679.59 2.98E10 1813.90 8.62E10 71.89 3.15E11 159.20 7.57E11 1.09 4.78E13 10.30 4.90E12 EVESR First Floor 2.83E+06 3227.29 1.42E09 7953.80 3.78E09 718.89 3.15E10 1551.40 7.37E10 0.29 1.27E13 5.20 2.47E12 Basement 2.83E+06 4923.19 2.16E09 11385.50 5.41E09 999.79 4.38E10 2181.90 1.04E09 2.49 1.09E12 75.60 3.59E11 519' Level 2.83E+06 6876.69 3.02E09 16930.10 8.05E09 1534.89 6.73E10 3353.20 1.59E09 1.09 4.78E13 59.90 2.85E11 GETR First Floor 2.83E+06 190.09 8.33E11 548.50 2.61E10 71.99 3.16E11 170.30 8.09E11 1.29 5.66E13 8.00 3.80E12 Basement 2.83E+06 99.59 4.37E11 245.00 1.16E10 29.29 1.28E11 76.60 3.64E11 1.09 4.78E13 15.00 7.13E12 Third Floor 2.83E+06 124.29 5.45E11 458.30 2.18E10 43.29 1.90E11 238.00 1.13E10 0.79 3.46E13 43.30 2.06E11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%
Beta Efficiency 33.47%
dpm/uCi 2.22E+06 Alpha cpm/uCi 8.05E+05 Beta cpm/uCi 7.43E+05 Sampling Information Flow Initial 1 Hr Approx.
Minutes Rate Total Total Sample Count Count Minutes HalfLife Reactor Location Date Sampled Time On Time Off sampled (cfm) Flow (ft3) ml/ft3 Volume (ml) Time Time Decay (min.)
VBWR First Floor 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:54 9:52 58 34.3 VBWR Basement 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:42 9:42 60 36.2 VBWR Fuel Pool 6/25/2019 9:43 10:03 20 5 100.0 28317 2.83E+06 10:16 12:10 114 35.2 EVESR First Floor 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:39 11:55 76 35.1 EVESR Basement 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:49 12:05 76 33.0 EVESR 519' Level 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:28 11:44 76 35.1 GETR First Floor 6/17/2019 14:17 14:37 20 5 100.0 28317 2.83E+06 14:45 15:49 64 45.7 GETR Basement 6/17/2019 9:50 10:10 20 5 100.0 28317 2.83E+06 10:58 12:00 62 35.1 GETR Third Floor 6/25/2019 8:55 9:15 20 5 100.0 28317 2.83E+06 9:36 10:36 60 39.4
- HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 52 FOR THE YEAR 2019 LICENSE DR-10 DOCKET 50-183 MARCH 2020
EVESR Annual Report No. 52 ESADA-Vallecitos Experimental Superheat Reactor (Deactivated)
ANNUAL REPORT NO. 52 GE Hitachi Nuclear Energy (GEH) has maintained the ESADA Vallecitos Experimental Superheat Reactor (EVESR) in a deactivated status under the authority of Amendment No. 7 to License DR-10, Docket 50-183, issued December 1, 2008. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented, as required by Amendment 7, Appendix A, Technical Specifications, section C. 1.
1.0
SUMMARY
Component removal activities began in 2008 above the 549-foot level. Tech Spec changes issued in Amendment 7 December 1, 2008 authorize the removal of systems beside the reactor vessel and bio-shield below the 549-level. Component removal concluded (current scope) in 2010. Entry into the containment building was made for routine radiation surveys and a general examination of conditions throughout the building. In accordance with written procedures, the Facility Manager controls access to the containment building.
Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review.
2.0 STATUS OF FACILITY The facility continues to be in deactivated status. The plugs to the reactor vessel and head storage shield, the wooden cover over the fuel storage pool remain in place.
3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low. Results of the surveys are presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.
An assessment for radionuclide distribution was performed of the shutdown reactors.
An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.
Page 1 of 3
EVESR Annual Report No. 52 3.1 GROUND WATER MONITORING WELL Groundwater well MW-9 was installed southwest of the EVESR and VBWR shutdown reactors. Monitoring Well 9 has two sampling points documented as MW-9S and MW-9D. These wells will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of the shutdown reactors in this area. The installation of these wells is part of the response letter to the NRC, NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules, GEH Response Summary Dated May 31, 2019. Analytical results of groundwater samples collected from the wells during the reporting periods. These wells were sampled quarterly after installation in 2019.
Well W-9S (4S-1E2P1)
Month Gross Alpha Gross Beta Tritium (pCi/L) (pCi/L) (pCi/L)
July 2019 2.81 1.62 0 October 2019 2.31 2.82 176 Annual Average 2.56 2.22 88 Well W-9D (4S-1E2P2)
Month Gross Alpha Gross Beta Tritium (pCi/L) (pCi/L) (pCi/L)
July 2019 5.04 2.29 395 October 2019 4.10 0.75 270 Annual Average 4.57 1.52 333 4.0 ACTIVITIES Routine inspections were conducted during this report period. During this report period, two additional monitoring wells were installed downgradient of EVESR. No major activities occurred inside the reactor during this period.
5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The EVESR Facility Manager remains K. P.
Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.
6.0 CONCLUSION
GE Hitachi Nuclear Energy concludes that the deactivated ESADA-Vallecitos Experimental Superheat Reactor is being maintained in a safe shutdown condition. The Page 2 of 3
EVESR Annual Report No. 52 inspections, access control, and administratively controlled activities ensure maximum protection for the public health and safety. The procedures will be continued to maintain this high level of protection.
GE Hitachi Nuclear Energy Vallecitos Operations Manager Vallecitos Nuclear Center Page 3 of 3
Attachment 1 SURVEYOR (print and sign) REVIEWER NO.
g HITACHI Name and signature on original at GEH Vallecitos Nuclear Center LOCATION DATE:
D-056 06/18/19 VALLECITOS NUCLEAR CENTER TIME:
NUCLEAR SAFETY SURVEY RECORD EVESR Containment 1100 Routine REASON Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item n TOTAL Distance No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 487' Level (Basement) <1 <1 F 2 503' Level <1 <1 F 3 519' Level <1 <1 F 4 534' Level - General Area 1.5 1.5 C 5 - Floor Drain 7 7 C 6 - Floor Drain @ 1' 1.5 1.5 C 7 - Emergency Cooling Valves 4.5 4.5 F 8
9 549' Level <1 <1 F 10 Equipment Air Lock <1 <1 F 11 Personnel Air Lock <1 <1 F 12 Top of Spent Fuel Pool (Main Floor) <0.5 <0.5 F 13 14 15 16 INSTRUMENT USED Tennelec PRM - 7 CP - 5 RO - 20 PNR - 4 TBM - E - 120 RM - 14 RM - 15 PAC - 1SA LUDLUM-12 SERIAL NUMBER 2972-1 6128 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE AC - 3A (U) 10% PROBE PANCAKE 20%
COMMENTS Smears completed on Tennelec see attachment EFF. 43 - 4 (U) 10% EFF.
Areas smeared are on maps with attachement (4 P (4 P GEO.) GEO.)
NEO 289 (REV. 07/10)
EVESR 549 Level
<1 5
6
<1 Escape Hatch 4
7 <1
<1
<1 3
8 9
<1
<1 10 11 2
<1 Stairs
<1
<1
<1 1 Equipment Hatch Dose Rates in mRem/hr
EVESR 534 Level 6
<1 Tank 5
<1 4 Rx Pipe Chase 9
<1
<1 8 1 Drain 7 contact 2 3 @ 30cm 3
<1 <1 7
Valve <1 3 contact 1 @ 30cm Stairs Valve 2 contact
<1 1 1 @ 30cm Dose Rates in mRem/hr
EVESR 519 Level 6
<1
<1
<1 4
Tank 5 <1
<1 Rx
<1 3
<1 Stairs Stairs 2
<1
<1 1
Dose Rates in mRem/hr
EVESR 503 Level
<1 5
<1 6 4 <1
<1 3
Pipe Chase Opening 8 <1 7
<1
<1 1 Rx Stairs
<1 Pipe Chase Opening 2
<1 Stairs Dose Rates in mRem/hr
EVESR 500 Level In-Core Flux Area Rx
<1 3
4 Stairs
<1
<1 1 Stairs 2
<1 Dose Rates in mRem/hr
EVESR 487 Level 10 <1
<1
<1 6
9
<1
<1 11
<1
<1 5 7 CRD Room
<1 Sump
<1 4
<1 8 <1
<1 <1 1
<1 Stairs
<1 3
<1 2
<1 Dose Rates in mRem/hr
Attachment to Survey D056: EVESR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument: Tennelec XLB System A Analyzed By:
Serial No.: 29722 Signature:
Calibration Date: 1 Mar 2019 Reviewed:
Beta Efficiency: 33.47% Beta MDA: 16.9 dpm Alpha Efficiency: 36.28% Alpha MDA: 10.5 dpm Sample Date: 6/18/19 Count Date: 6/18/19 Alpha Alpha Beta Beta Level Location (NCPM/100 cm2) (DPM/100 cm2) (NCPM/100 cm2) (DPM/100 cm2) 1 0 0 17.2 51.4 2 0 0 17.2 51.4 3 0 0 12.2 36.4 4 0.9 2.5 16.2 48.4 5 0.9 2.5 20.2 60.3 549 6 0 0 8.2 24.5 Level 1 7 0 0 10.2 30.5 8 0 0 12.2 36.4 9 0 0 14.2 42.4 10 0 0 18.2 18.2 11 1.9 5.2 37.2 37.2 1 0 0 120.2 359 2 0 0 153.2 458 3 0 0 482.2 1440 4 0 0 207.2 619 534 5 1.9 5.2 110.2 329 Level 2 6 0 0 95.2 284 7 0 0 176.2 526 8 0 0 36.2 108 9 0.9 2.5 108.2 323 10 (Fenced Area) 0.9 2.5 110.2 329 1 0 0 71.2 213 519 2 0 0 43.2 129 Level 3 3 0.9 2.5 76.2 228 4 0.9 2.5 189.2 565 Page 1 of 2
Attachment to Survey D056: EVESR Containment Annual Survey Smear Results Alpha Alpha Beta Beta Level Location (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm2) 2 2 (DPM/100 cm2) 5 0 0 77.2 231 6 0 0 48.2 144 1 0 0 111.2 332 2 0 0 883.2 2,640 3 2.89 8.0 124.2 371 503 4 0 0 78.2 234 Level 4 5 0 0 129.2 386 6 0 0 193.2 577 7 0 0 95.2 284 8 0.89 2.5 281.2 840 1 0 0 144.2 431 500 2 0 0 23.2 69.3 InCore 3 0 0 298.2 891 Flux Level 4 0 0 3650 10,900 1 0 0 106.2 317 2 0 0 326.2 975 3 1.89 5.2 130.2 389 4 1.89 5.2 140.2 419 5 0 0 47.2 141 487 6 0 0 68.2 204 Basement 7 0 0 118.2 353 8 0 0 244.2 730 9 0 0 210.2 628 10 0.89 2.5 335.2 1000 11 0.89 2.5 470.2 1400 Page 2 of 2
VBWR & EVESR SITE MAP 7 Mockup Equipment 8
Mockup 7
Equipment Concrete Pad EVESR
Background
1 Soil Sample 9 Mockup Area 8
10 EVESR 3 Soil Sample 9
8 Concrete Ring 11 9
8 8 Building Concrete Pad Cask Cask Cask 11 Concrete Pad EVESR 12 4 Soil Sample 8
12 Cask Cask al 10 son Per tch Ha Cask 14 EVESR Concrete Pad Ve n
12 io at il it nt Un 13 EVESR Equipment Hatch Stack 18 5 Soil Sample 6 VBWR
Background
Soil Sample 1 16 2 EVESR
Background
12 Soil Sample 20 22 Building EVESR Tank Pad 6 Soil Sample 30 5 VBWR Soil Sample Personal 32 Hatch 15 56 68 VBWR Equ ip VBWR Ha ment 4 Soil Sample tch VBWR 60 118 90
Background
Soil Sample 3 1000 VBWR
Background
Soil Sample 425 2 80 6 VBWR Soil Sample 410 180 Dose Rates in microRem/hr
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial 1 Hour Decay >24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E10 792.30 3.77E10 103.39 4.53E11 233.50 1.11E10 0.00 0.00E+00 7.00 3.33E12 Basement 2.83E+06 820.19 3.60E10 1991.90 9.47E10 260.29 1.14E10 592.20 2.81E10 0.49 2.15E13 21.50 1.02E11 Fuel Pool 2.83E+06 679.59 2.98E10 1813.90 8.62E10 71.89 3.15E11 159.20 7.57E11 1.09 4.78E13 10.30 4.90E12 EVESR First Floor 2.83E+06 3227.29 1.42E09 7953.80 3.78E09 718.89 3.15E10 1551.40 7.37E10 0.29 1.27E13 5.20 2.47E12 Basement 2.83E+06 4923.19 2.16E09 11385.50 5.41E09 999.79 4.38E10 2181.90 1.04E09 2.49 1.09E12 75.60 3.59E11 519' Level 2.83E+06 6876.69 3.02E09 16930.10 8.05E09 1534.89 6.73E10 3353.20 1.59E09 1.09 4.78E13 59.90 2.85E11 GETR First Floor 2.83E+06 190.09 8.33E11 548.50 2.61E10 71.99 3.16E11 170.30 8.09E11 1.29 5.66E13 8.00 3.80E12 Basement 2.83E+06 99.59 4.37E11 245.00 1.16E10 29.29 1.28E11 76.60 3.64E11 1.09 4.78E13 15.00 7.13E12 Third Floor 2.83E+06 124.29 5.45E11 458.30 2.18E10 43.29 1.90E11 238.00 1.13E10 0.79 3.46E13 43.30 2.06E11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%
Beta Efficiency 33.47%
dpm/uCi 2.22E+06 Alpha cpm/uCi 8.05E+05 Beta cpm/uCi 7.43E+05 Sampling Information Flow Initial 1 Hr Approx.
Minutes Rate Total Total Sample Count Count Minutes HalfLife Reactor Location Date Sampled Time On Time Off sampled (cfm) Flow (ft3) ml/ft3 Volume (ml) Time Time Decay (min.)
VBWR First Floor 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:54 9:52 58 34.3 VBWR Basement 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:42 9:42 60 36.2 VBWR Fuel Pool 6/25/2019 9:43 10:03 20 5 100.0 28317 2.83E+06 10:16 12:10 114 35.2 EVESR First Floor 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:39 11:55 76 35.1 EVESR Basement 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:49 12:05 76 33.0 EVESR 519' Level 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:28 11:44 76 35.1 GETR First Floor 6/17/2019 14:17 14:37 20 5 100.0 28317 2.83E+06 14:45 15:49 64 45.7 GETR Basement 6/17/2019 9:50 10:10 20 5 100.0 28317 2.83E+06 10:58 12:00 62 35.1 GETR Third Floor 6/25/2019 8:55 9:15 20 5 100.0 28317 2.83E+06 9:36 10:36 60 39.4
- HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 61 FOR THE YEAR 2020 LICENSE TR-1 DOCKET 50-70 MARCH 2020
GETR Annual Report No. 61 General Electric Test Reactor (Deactivated)
ANNUAL REPORT NO. 61 GE Hitachi (GEH) has maintained the General Electric Test Reactor (GETR) in a deactivated status under the authority of Amendment No. 17 to License TR-1, Docket 50-70, issued October 22, 2007, as specified in TS 6.6.1 to Amendment No. 14, issued February 5, 1986. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented.
1.0
SUMMARY
The facility remains in essentially the same condition described in Annual Report No. 60.
Entry into the reactor building was made for routine radiation surveys and a general examination of conditions throughout the building. The crane, elevator, and ventilation were serviced and tested in 2011 in anticipation of beginning remediation activities.
Such activities have not begun.
Radiation and contamination levels remain at acceptable levels.
2.0 STATUS OF FACILITY In accordance with written procedures, the Facility Manager controls access to the containment building and general systems. The facility continues to be in deactivated status. There were no changes authorized by the Facility Manager pursuant to 10CFR50.59(a) in 2019.
3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low. Results of the surveys are presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.
Radiological surveys were performed in June 2019, in unknown areas that had not been surveyed previously using Change Authorization 19-05. Entries into these areas was Page 1 of 4
GETR Annual Report No. 61 performed using SCBA and full-face respiratory protection. Radiological surveys are available for review at VNC. Some of the areas were found to have high radiation levels and high levels of contamination. Areas were posted as required by regulation based on survey results.
An assessment for radionuclide distribution was performed of the shutdown reactors.
An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.
3.1 GETR Stack Although maintenance was performed on the stack in 2011, and the stack was tested, there has been no remediation effort performed for the GETR reactor. The ventilation system is operational, but not currently in use.
GETR Stack was operational from June to November 2019, during entries made into unknown areas for surveying purposes. The data listed below is from the GETR stack.
GETR Stack Month Beta (uCi) Alpha (uCi)
May 2019 0.00 1.77E-02 June 2019 3.48E-03 3.67E-01 July 2019 1.39E-03 6.36E-02 August 2019 7.33E-03 5.59E-01 September 2019 6.57E-03 1.78E-01 October 2019 5.74E-03 1.14E-01 November 2019 6.91E-03 1.73E-01 Total (Annual) 3.14E-02 1.47E+00 3.2 Gamma Radiation The yearly dose results for the year 2019 as determined from evaluation of site perimeter environmental monitoring dosimeters showed no departure from normal stable backgrounds.
3.3 Vegetation No alpha, beta or gamma activity attributable to activities at the GETR facility was found on or in vegetation in the vicinity of the site.
Page 2 of 4
GETR Annual Report No. 61 3.4 Ground Water Monitoring Well Data Analytical results of groundwater samples collected from the B-2 (GETR) well during the reporting periods. The GETR well was sampled quarterly in 2019. During the fourth quarter sampling period, a sample was not collected from the B-2 well due to a blockage caused by the sampling bag. Condition Report # 33068 was entered into the Condition Report System.
GETR Well B-2 Month Gross Gross Beta Tritium Alpha (pCi/L) (pCi/L)
(pCi/L)
January 2019 9.36 2.76 522 April 2019 3.93 3.24 149 August 2019 6.50 2.47 318 November 2019 No Sample Collected CR # 33068 Groundwater well MW-8 was installed southwest of the GETR shutdown reactor. The well will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of GETR. The installation of the well is part of the response letter to the NRC, NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules, GEH Response Summary Dated May 31, 2019. Well was sampled quarterly in 2019 after installation.
Well W-8 (4S-1E2M01)
Month Gross Alpha Gross Beta Tritium (pCi/L) (pCi/L) (pCi/L)
July 2019 6.86 1.51 371 October 2019 1.32 2.28 798 Annual Average 4.09 1.90 585 4.0 ACTIVITIES Routine inspections were conducted during this report period. A small amount of water
(<5 gallon) was identified in the elevator sump area of GETR. The water was removed (CR# 31626), and gamma spectroscopy was performed. Results were normal. There were no preventive or corrective maintenance activities performed having safety significance during the reporting period.
5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The GETR Facility Manager remains K. P.
Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.
Page 3 of 4
GETR Annual Report No. 61
6.0 CONCLUSION
GE Hitachi Nuclear Energy concludes that the deactivated GETR is being maintained in a safe shutdown condition. The inspections, access control, and admin istratively controlled activities ensure maximum protection for the public health and safety. The procedures will be continued to maintain this high level of protection.
GE Hitachi Nuclear Energy Vallecitos Operations 3f/?r Manager Vallecitos Nuclear Center Page 4of4
Attachment 1 SURVEYOR (print and sign) REVIEWER NO.
g HITACHI Name and signature on original at GEH Vallecitos Nuclear Center LOCATION DATE:
C-020 06/17/19 VALLECITOS NUCLEAR CENTER TIME:
NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (1 of 2) 1100 Routine REASON Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item n TOTAL Distance No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Personnel Air Lock <1 <1 F 2 Equipment Air Lock <1 <1 F 3 Personnel Air Lock SOP 4 1st - Clean Area <1 <1 F 5 - Zone Area <1 <1 F 6 2nd - General Dose Rate <1 <1 F 7 - EEHS Cubicle Door 7 7 C 8 - Field Reading Around EEHS Cubicle <1-5 <1-5 F 9 - Filter Bank <1 <1 C 10 - Filter Bank Down stairs <1-5 <1-5 F 11 3rd - Zone Area North <1-1.5 <1-1.5 F 12 - Zone Area South <1-1 <1-1 F 13 - Bridge 1.5 1.5 F 14 - Missile Shield <1 <1 F 15 - Platform <1 <1 F 16 - Clean Area <1 <1 F INSTRUMENT USED Tennelec PRM - 7 CP - 5 RO - 20 PNR - 4 TBM - E - 120 RM - 14 RM - 15 PAC - 1SA LUDLUM-12 SERIAL NUMBER 2972-1 6128 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE AC - 3A (U) 10% PROBE PANCAKE 20%
COMMENTS Smears completed on Tennelec see attachment EFF. 43 - 4 (U) 10% EFF.
Areas smeared are on maps with attachement (4 P (4 P GEO.) GEO.)
NEO 289 (REV. 07/10)
SURVEYOR (print and sign) REVIEWER NO.
g HITACHI Name and signature on original at GEH Vallecitos Nuclear Center LOCATION DATE:
C-020 06/17/19 VALLECITOS NUCLEAR CENTER TIME:
NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (2 of 2) 1100 Routine REASON Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item n TOTAL Distance No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 3rd Floor - Zone Area Floor Drain 6 6 C 2 Elevator <1 <1 F 3 Basement - Clean Area <1 <1 F 4 - Filter Bank <1 <1 F 5 - Zone Area <1-3 <1-3 F 6 - Control Rod Storage <1 <1 C 7 - Control Rod Repair Hood <1 <1 C 8 - Autoclave 2 2 C nd rd 9 Mezzanine between 2 & 3 Floors <1 <1 F 10 B-1 Basement G/A <1-5 <1-5 F 11 B-1 Basement Pipe 120 120 C 12 B-1 Basement Pipe @1' 15 15 1' 13 B-2/B-4 Basment G/A <1 <1 F 14 B-3 Basement G/A <1 <1 F 15 Heat Exchange 25 25 C 16 Heat Exchange Room G/A <1 <1 INSTRUMENT USED Tennelec PRM - 7 CP - 5 RO - 20 PNR - 4 TBM - E - 120 RM - 14 RM - 15 PAC - 1SA LUDLUM-12 SERIAL NUMBER 2972-1 6128 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE AC - 3A (U) 10% X PROBE PANCAKE 20% X COMMENTS Smears completed on Tennelec see attachment EFF. 43 - 4 (U) 10% EFF.
Areas smeared are on maps with attachement (4 P (4 P GEO.) GEO.)
NEO 289 (REV. 07/10)
GETR Basement
<1 Cylin Stora der ge Are k a r Ban Filte
<1
<1
<1 SOP 67 68 25 contact CRD Rack
<1 <1 51 60 contact <1
- 10 @ 30cm 70 <1
- 60 69 1 CRD Hood 2 57
<1 61 56 Stairs
<1 <1 Hx 64
- Rx 62 120 contact <1 65 15 @ 30cm 3 <1 63 52
<1 <1 <1 66 53 <1
<1 59 SOP 55 Autoclave 2
58 Elevator
<1
<1 54
- = Dose Rate
- = Smear Location Dose Rates in mR/hr
GETR Level 1
<1 44 39 <1 46 38
<1 43 42
<1 SO P
<1 15 contact 37 6 @ 30cm
<1 EQUIPMENT HATCH STAIRS <1
<1 48 40
<1
<1 41
<1
<1 47 49 Elevator <1 50
<1 SOP PERS ONA L HA
- = Dose Rate TCH
- = Smear Location Dose Rates in mR/hr
GETR Level 2 STAIRS
<1 36
<1 35
<1 EEHS or Do <1
- 7 contact 4 @ 30cm STAIRS Rx 34
<1 27 33
<1 28
<1 29 10 contact 32
<1 Elevator
<1 30 31
<1
- = Dose Rate
- = Smear Location Dose Rates in mR/hr
GETR Level 3 Mezzine 25 26 <1 4
<1 3
<1
<1 2
STAIRS Rx
<1 1 <1 Elevator
- = Dose Rate
- = Smear Location Dose Rates in mR/hr
GETR Level 4 6 Opening
<1
<1 19 21 <1 20 16 <1
<1 Raised Platform Area
<1
<1 18 15 <1
<1 14 Opening 24 5
<1 Fuel Bridge 17 STAIRS Reactor Head 11 Reactor Cavity 23 &
Missile Shield
<1 13 <1
<1 7
<1 <1 12
<1 Drain
- 51.5contact
@ 30cm 8
<1 <1 22 <1 9
Elevator Office
<1
<1 10 Bathroom
- = Dose Rate
- = Smear Location Dose Rates in mR/hr
Attachment to Survey C020: GETR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument: Tennelec XLB System A Analyzed By:
Serial No.: 29722 Signature:
Calibration Date: 1 Mar 2019 Reviewed:
Beta Efficiency: 33.47% Beta MDA: 16.9 dpm Alpha Efficiency: 36.28% Alpha MDA: 10.5 dpm Sample Date: 6/17/19 Count Date: 6/17/19 Alpha Alpha Beta Beta Level Location (NCPM/100 cm2) (DPM/100 cm2) (NCPM/100 cm2) (DPM/100 cm2) 1 (Zone Floor) 0.9 2.5 72 216 2 (Zone Floor) 0.9 2.5 63 189 3 (Zone Floor) 0.0 0.0 335 1,001 4 (Zone Flats) 0.9 2.5 42 126 5 (Zone Flats) 0.0 0.0 24 72 6 (Zone Floor Left of SOP) 0.0 0.0 598 1,787 Main 7 (Zone Floor Right of SOP) 0.0 0.0 340 1,016 Floor 8 (By Ladder) 0.0 0.0 1,075 3,212 Level 1 Flats behind GE Logo 0.0 0.0 17 51 Floor Behind GE Logo 0.9 2.5 67 201 CA Area Floor Near Entrance 0.0 0.0 15 45 Equipment Air Lock 0.0 0.0 1 4 Clean Floor Near Entrance 0.9 2.5 26 78 Personnel Air Lock SOP 0.0 0.0 1 4 Zone Area CRD Rack 0.0 0.0 61 183 Zone Area Table 0.9 2.5 35 105 Heat Exchanger (HX) Room 0.0 0.0 25 75 Elevator 0.9 2.5 32 96 Clean Area 0.0 0.0 17 51 Basement Zone Area Rod Repair Hood 3.9 10.7 12,174 36,373 Zone Area Floor 0.0 0.0 548 1,638 Room B3 Flats 0.0 0.0 151 452 Room B3 Floor 0.0 0.0 42 126 Room B3 Floor @ Door 0.9 2.5 925 2,764 Under Vessel Flats 1.9 5.2 75 225 Page 1 of 3
Attachment to Survey C020: GETR Containment Annual Survey Smear Results Alpha Alpha Beta Beta Level Location (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm ) (DPM/100 cm2) 2 2 2 Under Vessel Floor 0.9 2.5 157 470 Under Vessel Rust Floor 0.0 0.0 1,322 3,950 Basement: Under HX Room 0.9 2.5 59 177 HX Room Lead Shield 0.9 2.5 21 63 HX Room Flats/Pipes 0.9 2.5 54 162 Basement Pump Room (B1) 0.0 0.0 117 350 Pump Room (B1) Floor 0.0 0.0 60 180 Pump Room (B1) Flats 0.0 0.0 64 192 Pump Room (B1) Floor 0.0 0.0 60 180 Inside, Only Entrance Hot Spot 0.0 0.0 2,917 8,716 Only Entrance Pump 0.0 0.0 261 780 Only Entrance Drain 0.0 0.0 2,575 7,694 Elevator 0.9 2.5 11 33 1 0.0 0.0 3 10 Level 2 2 0.0 0.0 6 19 3 0.0 0.0 31 93 4 (@ Stairs) 0.9 2.5 41 123 5 0.9 2.5 47 141 6 (@ Back Stairs Area) 0.9 2.5 34 102 Room 1 Floor 0.9 2.5 138 413 Room 1 Flats 1.9 5.2 157 470 Level 2.5 General Area 1 1.9 5.2 11 33 Mezzanine General Area 2 1.9 5.2 18 54 General Area 3 0.0 0.0 32 96 Top of Bathroom 0.9 2.5 39 117 Under Platform #1 Floor 0.9 2.5 39 117 Under Platform #2 Floor 0.0 0.0 129 386 Floor (1) @ Stairs 0.0 0.0 100 299 Floor (2) Left of Stairs 0.0 0.0 26 78 Floor (3) @ Bathroom 0.0 0.0 50 150 Level 3 Floor (4) @ Elevator 0.0 0.0 36 108 Top Floor Floor (5) @ Platform Stairs 0.9 2.5 135 404 Floor (6) Left of Missile Shield 0.0 0.0 354 1,058 Floor (7) Left side of Cavity 0.0 0.0 444 1,327 Floor (8) Right of Missile Shield 0.0 0.0 211 631 Floor (9) Right of Cavity 0.0 0.0 2,944 8,797 Floor (10) By Straight Ladder 0.0 0.0 1,083 3,236 Page 2 of 3
Attachment to Survey C020: GETR Containment Annual Survey Smear Results Alpha Alpha Beta Beta Level Location (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm ) (DPM/100 cm2) 2 2 2 Missile Shield (11) 0.0 0.0 147 440 Upper Deck (12) 0.9 2.5 24 72 Upper Deck (13) 2.9 8.0 48 144 Upper Deck (14) 0.0 0.0 32 96 Level 3 Flats (15) 0.0 0.0 23 69 Top Floor Flats (16) 3.9 10.7 127 380 Bridge (17) 0.9 2.5 234 700 Flats Spreader Bar (18) 0.9 2.5 131 392 Alpha Alpha Beta Beta Level Location (NCPM) (DPM) (NCPM) (DPM)
EEHS Floor 1 76.9 211.9 334207 998527 EEHS Floor 2 21.9 60.3 31243 93346 EEHS Floor 3 3.9 10.7 73920 220855 EEHS Flats 1 5.9 16.2 36608 109376 Level 2 EEHS Flats 2 0.9 2.5 24.2 72.3 EEHS Flats 3 7.9 21.7 9786 29238 EEHS Flats 4 0.9 2.5 2370 7081 EEHS Flats 5 9.9 27.3 29546 88276 Note: The smears in the Experiment Effluent Holdup System (EEHS) room were taken with disk smears, but were not limited to 100 cm2.
Page 3 of 3
GETR Site Map Building d
lan Sea d
d lan 17 lan Sea Sea d l and lan Sea Sea d
and lan l Sea 9
GETR 3 Soil Sea 1000 35 Sample nd Seala 19 la nd Sea Building 8
Building 40 60 Hatch 24 Equipment 14 20 30 tio ila nt it 25 GETR Ve Un 4 Soil n Sample 32 GETR 25 Personal Hatch GETR 1
Background
Soil Sample 36 50 Building 60 47 GETR 300 5 Soil Sample 22 1000 800 Tank 450 1200 Storm Drain 600 50 GETR 2 900 GETR Background 1100 6 Soil 350 Soil 28 Sample Sample 300 Building 9
35 14 20 17 # = Dose Rate
- = Soil Sample Location Dose Rates in microRem/hr
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial 1 Hour Decay >24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E10 792.30 3.77E10 103.39 4.53E11 233.50 1.11E10 0.00 0.00E+00 7.00 3.33E12 Basement 2.83E+06 820.19 3.60E10 1991.90 9.47E10 260.29 1.14E10 592.20 2.81E10 0.49 2.15E13 21.50 1.02E11 Fuel Pool 2.83E+06 679.59 2.98E10 1813.90 8.62E10 71.89 3.15E11 159.20 7.57E11 1.09 4.78E13 10.30 4.90E12 EVESR First Floor 2.83E+06 3227.29 1.42E09 7953.80 3.78E09 718.89 3.15E10 1551.40 7.37E10 0.29 1.27E13 5.20 2.47E12 Basement 2.83E+06 4923.19 2.16E09 11385.50 5.41E09 999.79 4.38E10 2181.90 1.04E09 2.49 1.09E12 75.60 3.59E11 519' Level 2.83E+06 6876.69 3.02E09 16930.10 8.05E09 1534.89 6.73E10 3353.20 1.59E09 1.09 4.78E13 59.90 2.85E11 GETR First Floor 2.83E+06 190.09 8.33E11 548.50 2.61E10 71.99 3.16E11 170.30 8.09E11 1.29 5.66E13 8.00 3.80E12 Basement 2.83E+06 99.59 4.37E11 245.00 1.16E10 29.29 1.28E11 76.60 3.64E11 1.09 4.78E13 15.00 7.13E12 Third Floor 2.83E+06 124.29 5.45E11 458.30 2.18E10 43.29 1.90E11 238.00 1.13E10 0.79 3.46E13 43.30 2.06E11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%
Beta Efficiency 33.47%
dpm/uCi 2.22E+06 Alpha cpm/uCi 8.05E+05 Beta cpm/uCi 7.43E+05 Sampling Information Flow Initial 1 Hr Approx.
Minutes Rate Total Total Sample Count Count Minutes HalfLife Reactor Location Date Sampled Time On Time Off sampled (cfm) Flow (ft3) ml/ft3 Volume (ml) Time Time Decay (min.)
VBWR First Floor 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:54 9:52 58 34.3 VBWR Basement 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:42 9:42 60 36.2 VBWR Fuel Pool 6/25/2019 9:43 10:03 20 5 100.0 28317 2.83E+06 10:16 12:10 114 35.2 EVESR First Floor 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:39 11:55 76 35.1 EVESR Basement 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:49 12:05 76 33.0 EVESR 519' Level 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:28 11:44 76 35.1 GETR First Floor 6/17/2019 14:17 14:37 20 5 100.0 28317 2.83E+06 14:45 15:49 64 45.7 GETR Basement 6/17/2019 9:50 10:10 20 5 100.0 28317 2.83E+06 10:58 12:00 62 35.1 GETR Third Floor 6/25/2019 8:55 9:15 20 5 100.0 28317 2.83E+06 9:36 10:36 60 39.4