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{{Adams
#REDIRECT [[M180070, GEH Annual Shutdown Reactor Reports for the Year 2017]]
| number = ML18088A736
| issue date = 03/29/2018
| title = GEH Annual Shutdown Reactor Reports for the Year 2017
| author name = Feyrer M
| author affiliation = GE Hitachi Nuclear Energy
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NMSS
| docket = 05000018, 05000070, 05000183
| license number = DPR-001, DR-010, TR-001
| contact person =
| case reference number = M180070
| document type = Annual Operating Report, Letter
| page count = 18
}}
 
=Text=
{{#Wiki_filter:* HITACHI M180070 March 29, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001 GE Hitachi Nuclear Energy Matt J. Feyrer Site Manager, Vallecitos Nuclear Center &7os vallecitos Rd Sunol, CA 94586 USA T 925 918 6018 Miltt.feyrer@lge.com Subject GEH Annual Shutdown Reactor Reports for the Year 2017  
 
==References:==
License DPR-1, Docket 50-18 (VBWR), License DR-10, Docket 50-183 (EVESR), License TR-1, Docket 50-70 (GETR) Enclosed are the 2018 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 eyrer, Site Manager Vallecitos Nuclear Center
 
==Enclosures:==
VBWR Annual Report No. 53, EVESR Annual Report No. 50, and GETR Annual Report No. 59 cc: NRC Region IV Administrator J. Parrott, NRC NMSS MJF 18-003
* HITACHI GE Hitachi Nuclear Energy VALLECITOS BOILING WATER REACTOR (DEACTIVATED) ANNUAL REPORT NO. 53 FOR THE YEAR 2017 LICENSE DPR-1 DOCKET 50-18 MARCH 2018 Vallecitos Nuclear Center Sunol, California VBWR Annual Report No. 53 Vallecitos Boiling Water Reactor (Deactivated) Annual Report No. 53 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, 2017 to December 31, 2017 is presented, as required by paragraph S.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. Page 1 of 2 VBWR Annual Report No. 53 4.0 ACTIVITIES Routine inspections were conducted during this report period. No other significant activities occurred at VBWR. 5.0 ORGANIZATION The organizational structure remained unchanged during 2017. The Site Manager remains M. J. Feyrer. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS, T. M. lelk, retired January 2018. J. G. Ayala is currently Acting Manager, Regulatory Compliance and EHS.
 
==6.0 CONCLUSION==
GE Hitachi Nuclear Energy concludes that the deactivated VBWR is being maintained in a safe shutdown condition. The 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 Page 2 of 2 SURVEYOR (print and sign) I REVIEWER NO. 8 HITACHI Name and signatures on Original at GEH Vallecitos D-0105 LOCATION DATE: VALLECITOS NUCLEAR CENTER 12/09/17 NUCLEAR SAFETY SURVEY RECORD VBWR Containment TIME: 0930 IRI Routine REASON D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item Jl y n TOTAL Distance Jly llr n n Pr llr a n No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Main Floor -General Area <I <I F <100 <500 <20 <200 100 em 2 -Area Over Reactor Vessel <I <I F <100 <500 <20 <200 100 em 3 4 Basement -General Area* N/A N/A F <100 <500 <20 <200 100 em 5 -Sump* N/A N/A c <100 <500 <20 <200 IOOem 6 7 Reactor Vessel Head Area <I <I F <100 <500 <20 <200 100 em 8 9 Top of Fuel Pool <I <I F <100 <500 <20 <200 100 em 10 11 Personnel Air Lock <I <I F <100 <500 <20 <200 100 em 12 13 Equipment Air Lock <I <I F <100 <500 <20 <200 100 em 14 15 16 INSTRUMENT USED PRM-7 CP-5 RO -20 PNR-4 TBM-E-120 RM-RM-PAC -1SA LUDLUM-12 SERIAL NUMBER 4549 1385 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE u AC-3A (U) 10% X PROBE py PANCAKE 20% X FOMMENTS
* No entry to basement due to water in basement. EFF. u 43-4 (U) 10% EFF. (4 p (4 p GEO.) GEO.) ---NEO 289 (REV. 07/10)
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2017 Initial Sample Alpha Beta Reactor location Volume (ml) ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 1281.30 6.22E-10 3323.20 1.68E-09 Basement 2.83E+06 1562.70 7.59E-10 4024.SO 2.03E-09 Fuel Pool 2.83E+06 1826.10 8.87E-10 4696.60 2.37E-09 EVESR First Floor 2.83E+06 5906.20 2.87E-09 16961.60 8.S7E-09 Basement 2.83E+06 4734.SO 2.30E-09 128S9.00 6.50E-09 S19' level 2.83E+06 4021.00 1.95E-09 10887.10 S.SOE-09 GETR First Floor 2.83E+06 1689.80 8.21E-10 4508.90 2.28E-09 Basement 2.83E+06 1645.90 7.99E-10 4496.20 2.27E-09 Third Floor 2.83E+06 1455.10 7.07E-10 3746.50 1.89E-09 Tennelec System "B" Efficiency & Conversion Factors Reactor VBWR VBWR VBWR EVESR EVESR EVESR GETR GETR GETR Alpha Efficiency 32.76% Beta Efficiency* dpm/uCi Alpha cpm/uCi Beta cpm/uCi Location First Floor Basement Fuel Pool First Floor Basement 519' level First Floor Basement Third Floor 31.49% 2.22E+06 7.27E+05 6.99E+OS Date Sameled 12/6/2017 11/2/2016 11/2/2016 11/1/2016 11/2/2016 11/2/2016 11/2/2016 11/2/2016 -11/2/2016_ Time On 16:10 10:07 9:45 9:00 12:58 12:35 14:13 14:36 15:00 --Sampling Information Minutes Flow Rate Time Off sameled (dm) 16:30 20 5 10:27 20 5 10:05 20 5 9:20 20 5 13:18 20 5 12:55 20 5 14:33 20 s 14:56 20 5 20 5 -1 Hour Decay 24/48 Hour Decay Alpha Beta Alpha Beta ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml 541.10 2.63E-10 1221.80 5.93E-10 2.80 1.36E-12 8.60 4.34E-12 805.50 3.91E-10 1827.70 8.87E-10 0.60 2.91E-13 5.80 2.93E-12 811.70 3.94E-10 18SS.40 9.01E-10 1.10 5.34E-13 11.10 5.61E-12 288S.60 1.40E-09 6429.30 3.12E-09 2.30 1.12E-12 s.oo 2.S3E-121 2424.70 1.18E-09 SS72.80 2.71E-09 1.20 5.83E-13 42.70 2.16E-11 2119.60 1.03E-09 4804.20 2.33E-09 1.60 7.77E-13 5.70 2.88E-12 628.80 3.05E-10 1397.40 6.79E-10 5.30 2.57E-12 15.50 7.83E-121 764.30 3.71E-10 1741.70 8.46E-10 1.10 S.34E-13 17.00 8.59E-121 798.90 3.88E-10 1859.80 9.03E-10 1.00 4.86E-13 23.ib 1.20E-11 Initial 1 Hr Aeerox. Total Total Samele Volume Samele Samele Minutes Half-Life Flow (ft3) ml/ft3 !!!ill Time Time Decay (min.) 100.0 28317 2.83E+06 16:45 17:35 so 40.2 100.0 28317 2.83E+06 9:56 10:40 44 46.0 100.0 28317 2.83E+06 9:30 10:18 48 41.0 100.0 28317 2.83E+06 17:10 18:00 so 48.4 100.0 28317 2.83E+06 10:47 11:32 45 46.6 100.0 28317 2.83E+06 10:30 11:10 40 43.3 100.0 28317 2.83E+06 17:4S 18:35 so 3S.1 100.0 28317 2.83E+06 7:48 8:38 so 45.2 100.0 28317 2.83E+06 8:21 9:00 39 45.1 -*---
* HITACHI GE Hitachi Nuclear Energy ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED) ANNUAL REPORT NO. 50 FOR THE YEAR 2017 LICENSE DR-10 DOCKET 50-183 MARCH 2018 Vallecitos Nuclear Center Sunol, California EVESR Annual Report No. 50 ESADA-Vallecitos Experimental Superheat Reactor (Deactivated) ANNUAL REPORT NO. 50 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, 2017 to December 31, 2017 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. Page 1 of 2 EVESR Annual Report No. 50 4.0 ACTIVITIES Routine inspections were conducted during this report period. The equipment disposal concluded during 2010. 5.0 ORGANIZATION The organizational structure remained unchanged during 2017. The Site Manager remains M. J. Feyrer. The EVESR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS, T. M. Leik, retired January 2018. J. G. Ayala is currently Acting Manager, Regulatory Compliance and EHS.
 
==6.0 CONCLUSION==
GE Hitachi Nuclear Energy concludes that the deactivated ESAOA-Vallecitos Experimental Superheat Reactor is being maintained in a safe shutdown condition. The 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 Page 2 of 2 SURVEYOR (print and sign) I REVIEWER NO. -HITACHI Name and signatures on Original at GEH Vallecitos D-0106 LOCATION DATE: 12/09/17 VALLECITOS NUCLEAR CENTER NUCLEAR SAFETY SURVEY RECORD EVESR Containment TIME: 1030 IRl Routine REASON D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item II y n TOTAL Distance Jly Jly a a py Jly a a No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Top of Spent Fuel Pool (Main Floor) <I <I F <100 <500 <20 <200 IOOcm 2 3 487' Level (Basement) <I <I F 150 750 <20 <200 IOOcm 4 503' Level <I <I F <100 <500 <20 <200 IOOcm 5 519' Level <I <I F <100 <500 <20 <200 IOOcm 6 534' Level -General Area <I <I F <100 <500 <20 <200 IOOcm 7 8 -Emergency Cooling Valves 3 3 c 9 549' Level <0.5 <0.5 F <100 <500 <20 <200 IOOcm 10 11 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOcm 12 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 em 13 14 15 16 INSTRUMENT USED PRM -7 CP-5 RO -20 PNR-4 TBM-E -120 RM-RM-PAC-1SA LUDLUM-12 SERIAL NUMBER 4549 1385 897 Area Posted: {circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC-3A {U) 10% X PROBE py PANCAKE 20% X COMMENTS a 43-4 {U) 10% EFF. EFF. (4 p (4 p GEO.) GEO.) NEO 289 {REV. 07/10)
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2017 Initial Sample Alpha Beta Reactor Location Volume (ml) ncpm VBWR First Floor 2.83E+06 1281.30 Basement 2.83E+06 1S62.70 Fuel Pool 2.83E+06 1826.10 EVESR First Floor 2.83E+06 S906.20 Basement 2.83E+06 4734.SO S19' Level 2.83E+06 4021.00 GETR First Floor 2.83E+06 1689.80 Basement 2.83E+06 164S.90 Third Floor 2.83E+06 14SS.10 Tennelec System "B" Efficiency & Conversion Factors Reactor VBWR VBWR VBWR EVESR EVESR EVESR GETR GETR GETR Alpha Efficiency 32.76% Beta Efficiency dpm/uCi Alpha cpm/uCi Beta cpm/uCi Location First Floor Basement Fuel Pool First Floor Basement S19' Level First Floor Basement Third Floor 31.49% 2.22E+06 7.27E+OS 6.99E+OS Date Sameled 12/6/2017 11/2/2016 11/2/2016 11/1/2016 11/2/2016 11/2/2016 11/2/2016 11/2/2016 11/2/2016 Time On 16:10 10:07 9:4S 9:00 12:S8 12:3S 14:13 14:36 1S:OO uCi/ml ncpm uCi/ml 6.22E-10 3323.20 1.68E-09 7.S9E-10 4024.SO 2.03E-09 8.87E-10 4696.60 2.37E-09 2.87E-09 16961.60 8.S7E-09 2.30E-09 128S9.00 6.SOE-09 1.9SE-09 10887.10 S.SOE-09 8.21E-10 4S08.90 2.28E-09 7.99E-10 4496.20 2.27E-09 7.07E-10 3746.SO 1.89E-09 Sampling Information Minutes Flow Rate Time Off same led (dm) 16:30 20 s 10:27 20 s 10:0S 20 s 9:20 20 s 13:18 20 s 12:SS 20 s 14:33 20 s 14:S6 20 s 1S:20 20 s 1 Hour Decay 24/48 Hour Decay Alpha Beta Alpha Beta ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml S41.10 2.63E-10 1221.80 S.93E-10 2.80 1.36E-12 8.60 4.34E-12 80S.SO 3.91E-10 1827.70 8.87E-10 0.60 2.91E-13 S.80 2.93E-12 811.70 3.94E-10 18SS.40 9.01E-10 1.10 S.34E-13 11.10 S.61E-12 288S.60 1.40E-09 6429.30 3.12E-09 2.30 1.12E-12 s.oo 2.S3E-12 2424.70 1.18E-09 SS72.80 2.71E-09 1.20 S.83E-13 42.70 2.16E-11 2119.60 1.03E-09 4804.20 2.33E-09 1.60 7.77E-13 S.70 2.88E-12 628.80 3.0SE-10 1397.40 6.79E-10 S.30 2.S7E-12 1S.SO 7.83E-12 764.30 3.71E-10 1741.70 8.46E-10 1.10 S.34E-13 17.00 8.S9E-12 798.90 3.88E-10 18S9.80 9.03E-10 1.00 4.86E-13 23.70 1.20E-11 Initial 1 Hr Aeerox. Total Total Samele Volume Samele Samele Minutes Half-Life Flow (ft3) ml/ft3 !!!ill Time Time Decay (min.) 100.0 28317 2.83E+06 16:4S 17:3S so 40.2 100.0 28317 2.83E+06 9:S6 10:40 44 46.0 100.0 28317 2.83E+06 9:30 10:18 48 41.0 100.0 28317 2.83E+06 17:10 18:00 so 48.4 100.0 28317 2.83E+06 10:47 11:32 4S 46.6 100.0 28317 2.83E+06 10:30 11:10 40 43.3 100.0 28317 2.83E+06 17:4S 18:3S so 3S.1 100.0 28317 2.83E+06 7:48 8:38 so 4S.2 100.0 28317 2.83E+06 8:21 9:00 39 4S.1
* HITACHI GE Hitachi Nuclear Energy GENERAL ELECTRIC TEST REACTOR (DEACTIVATED) ANNUAL REPORT NO. 59 FOR THE YEAR 2017 LICENSE TR-1 DOCKET 50-70 MARCH 2018 Vallecitos Nuclear Center Sunol, California GETR Annual Report No. 59 General Electric Test Reactor (Deactivated) ANNUAL REPORT NO. 59 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. In this annual report, a summary of the status of the facility for the period of January 1, 2017 to December 31, 2017 is presented. l.OSUMMARY The facility remains in essentially the same condition described in Annual Report No. 54. 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 10CFRSO.S9(a) in 2017. 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. The data below are from sample and dosimeter results accumulated during 2017. These data are for the entire VNC site and include the effects of operations other than GETR. Page 1 of 3 GETR Annual Report No. 59 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. The ventilation system was not operated in 2017. 3.2 Gamma Radiation The yearly dose results for the year 2017 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. 3.4 GETR Well Analytical results of groundwater samples collected from the B-2 {GETR) well during the reporting periods. The March 2018 sample was collected due to a considerable amount of sediment found in the December 2017 sample. We will continue to monitor the results and perform a gamma scan on the sample if necessary. Month Gross beta pCi/L Gross Alpha pCi/L Tritium pCi/L June 2017 4.49 1.70 1656 December 2017 2.69 25.57 133 March 2018 0.00 8.86 949 Page 2 of 3 GETR Annual Report No. 59 4.0 ACTIVITIES Routine inspections were conducted during this report period. There were no preventive or corrective maintenance activities performed having safety significance during the reporting period. 5.0 ORGANIZATION The organizational structure remained unchanged during 2017. The Site Manager remains M. J. Feyrer. The GETR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS, T. M. Leik, retired January 2018. J. G. Ayala is currently Acting Manager, Regulatory Compliance and EHS.
 
==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 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 Page 3 of 3 SURVEYOR (print and sign) I REVIEWER NO. 8 HITACHI Name and signatures on Original at GEH Vallecitos C-041 LOCATION DATE: VALLECITOS NUCLEAR CENTER 12/09/17 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 1 of 2) TIME: 0800 lEI Routine REASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item p y n TOTAL Distance 1:\y fly a a py py a a No mRad/h mR/h mRem/h mRemlh CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Personnel Air Lock <I <I F <100 <500 <20 <200 100 em2 2 EQuipment Air Lock <I <I F <100 <500 <20 <200 100 em2 3 Personnel Air Lock SOP <100 <500 <20 <200 100 em2 4 1st Floor -Clean Area * <I <I F <100 <500 <20 <200 100 em2 5 -Zone Area* <1-4 <1-4 F <100 <500 <20 <200 100 em2 6 2nd Floor -General Dose Rate <I-I <I-I F 7 -EEHS Cubicle Door 8 8 c 8 -Field Reading Around EEHS Cubicle <1-2 <1-2 F 9 -Floor Smear I Clean Area * <100 <500 <20 <200 100 eml 10 -Filter Bank <I <I c 11 3rd Floor -Zone Area North I Floor * <1-3 <1-3 F <100 <500 <20 <200 100 em2 12 -Zone Area South <I <I F 600 3000 <20 <200 100 13 -Bridge I Canal I I F 800 4000 <20 <200 100 em 14 -Missile Shield Point A * <1-1.5 <1-1.5 F <100 <500 <20 <200 100 em 15 -Platform <I <I F <100 <500 <20 <200 100 em 16 -Clean Area * <I <I F <100 <500 <20 <200 IOOem INSTRUMENT USED PRM-7 CP-5 RO -20 PNR-4 TBM-E-120 RM-RM-PAC -1SA LUDLUM-12 SERIAL NUMBER 4549 1385 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE py PANCAKE 20% X <.;QMMENTS
* Whatman Smears EFF. a 43-4 (U) 10% EFF. 3rd floor zone north floor by Pool Svc Pump Cntrl: 28 mR/hr @C (4 p (4 p GEO.) GEO.) NEO 289 (REV. 0711 0)
SURVEYOR (print and sign) I REVIEWER NO. e HITACHI Name and signatures on Original at GEH Vallecitos C-041 LOCATION DATE: VALLECITOS NUCLEAR CENTER 12/09/17 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 1 of2) TIME: 0800 IBl Routine REASON D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item II y n TOTAL Distance 1\y fly a a fly py a a No. mRad/h mR/h mRem/h mRemlh CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Personnel Air Lock <I <I F <100 <500 <20 <200 100 em 2 Equipment Air Lock <I <I F <100 <500 <20 <200 100 em 3 Personnel Air Lock SOP <100 <500 <20 <200 100 em 4 1st Floor -Clean Area * <I <I F <100 <500 <20 <200 100 em 5 -Zone Area* <1-4 <1-4 F <100 <500 <20 <200 IOOem 6 2nd Floor -General Dose Rate <I-I <1-1 F 7 -EEHS Cubicle Door 8 8 c 8 -Field Reading Around EEHS Cubicle <1-2 <1-2 F 9 -Floor Smear I Clean Area * <100 <500 <20 <200 100 em 10 -Filter Bank <I <I c 11 3rd Floor -Zone Area North I Floor * <1-3 <1-3 F <100 <500 <20 <200 IOOem 12 -Zone Area South <I <I F 600 3000 <20 <200 100 em 13 -Bridge I Canal I I F 800 4000 <20 <200 100 em 14 -Missile Shield Point A * <1-1.5 <1-1.5 F <100 <500 <20 <200 100 em 15 -Platform <I <I F <100 <500 <20 <200 100 em 16 -Clean Area * <I <I F <100 <500 <20 <200 100 em INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM-E-120 RM-RM-PAC -1SA LUDLUM-12 SERIAL NUMBER 4549 1385 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE u AC-3A (U) 10% X PROBE llr PANCAKE 20% X COMMENTS
* Whatman Smears u 43-4 (U) 10% EFF. EFF. 3rd floor zone north floor by Pool Svc Pump Cntrl: 28 mRihr @C (4 p (4 p GEO.) GEO.) NEO 289 (REV. 07/10)
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2017 Initial Sample Alpha Beta Reactor location Volume (ml) ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 1281.30 6.22E-10 3323.20 1.68E-09 Basement 2.83E+06 1S62.70 7.59E-10 4024.SO 2.03E-09 Fuel Pool 2.83E+06 1826.10 8.87E-10 4696.60 2.37E-09 EVESR First Floor 2.83E+06 S906.20 2.87E-09 16961.60 8.57E-09 Basement 2.83E+06 4734.50 2.30E-09 128S9.00 6.SOE-09 S19' level 2.83E+06 4021.00 1.9SE-09 10887.10 S.SOE-09 GETR First Floor 2.83E+06 1689.80 8.21E-10 4S08.90 2.28E-09 Basement 2.83E+06 164S.90 7.99E-10 4496.20 2.27E-09 Third Floor 2.83E+06 14SS.10 7.07E-10 3746.SO 1.89E-09 Tennelec System "B" Efficiency & Conversion Factors Reactor VBWR VBWR VBWR EVESR EVESR EVESR GETR GETR GETR Alpha Efficiency 32.76% Beta Efficiency dpm/uCi Alpha cpm/uCi Beta cpm/uCi Location First Floor Basement Fuel Pool First Floor Basement S19' level First Floor Basement Third Floor 31.49% 2.22E+06 7.27E+OS 6.99E+OS Date 12/6/2017 11/2/2016 11/2/2016 11/1/2016 11/2/2016 11/2/2016 11/2/2016 11/2/2016 11/2/2016 Sampling Information Minutes Flow Rate Time On Time Off (dm) 16:10 16:30 20 s 10:07 10:27 20 s 9:4S 10:0S 20 s 9:00 9:20 20 s 12:S8 13:18 20 s 12:3S 12:SS 20 s 14:13 14:33 20 s 14:36 14:S6 20 s 1S:OO 1S:20 20 s 1 Hour Decay 24/48 Hour Decay Alpha Beta Alpha Beta ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uO/ml S41.10 2.63E-10 1221.80 S.93E-10 2.80 1.36E-12 8.60 4.34E-12 80S.SO 3.91E-10 1827.70 8.87E-10 0.60 2.91E-13 S.80 2.93E-12 811.70 3.94E-10 18SS.40 9.01E-10 1.10 S.34E-13 11.10 S.61E-12 288S.60 1.40E-09 6429.30 3.12E-09 2.30 1.12E-12 s.oo 2.53E-12 2424.70 1.18E-09 SS72.80 2.71E-09 1.20 S.83E-13 42.70 2.16E-11 2119.60 1.03E-09 4804.20 2.33E-09 1.60 7.77E-13 S.70 2.88E-12 628.80 3.0SE-10 1397.40 6.79E-10 S.30 2.S7E-12 1S.SO 7.83E-12 764.30 3.71E-10 1741.70 8.46E-10 1.10 S.34E-13 17.00 8.S9E-12 798.90 3.88E-10 18S9.80 9.03E-10 1.00 4.86E-13 23.70 1.20E-11 Initial 1 Hr Total Total Volume Minutes Half-Life Flow (ft3} ml/ft3 !!!ill Time Time Decay (min.} 100.0 28317 2.83E+06 16:4S 17:3S so 40.2 100.0 28317 2.83E+06 9:S6 10:40 44 46.0 100.0 28317 2.83E+06 9:30 10:18 48 41.0 100.0 28317 2.83E+06 17:10 18:00 so 48.4 100.0 28317 2.83E+06 10:47 11:32 4S 46.6 100.0 28317 2.83E+06 10:30 11:10 40 43.3 100.0 28317 2.83E+06 17:4S 18:3S so 3S.1 100.0 28317 2.83E+06 7:48 8:38 so 4S.2 100.0 28317 2.83E+06 8:21 9:00 39 4S.1 
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