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{{Adams
#REDIRECT [[M170076, GE-Hitachi Nuclear Energy Americas, LLC - Annual Shutdown Reactor Reports for 2017]]
| number = ML17083A160
| issue date = 03/23/2017
| title = GE-Hitachi Nuclear Energy Americas, LLC - Annual Shutdown Reactor Reports for 2017
| author name =
| author affiliation = GE-Hitachi Nuclear Energy Americas, LLC
| addressee name =
| addressee affiliation = NRC/NMSS
| docket = 05000018, 05000070, 05000183
| license number = DPR-001, DPR-010, TR-001
| contact person =
| case reference number = M170076
| package number = ML17083A156
| document type = Annual Operating Report
| page count = 17
}}
 
=Text=
{{#Wiki_filter:(. HITACHI VALLECITOS BOILING WATER REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 52 FOR THE VEAR 2016 LICENSE DPR-1 DOCKET 50-18 MARCH 2017 Vollecttos Nuclear Center Sunol, Coltformo VBWR Annual Report No. 52 Vallecitos Boiling Water Reactor (Deactivated)
Annual Report No. 52 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWRI 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. 2016 to December 31, 2016 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 FACIUTV 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 ond contaminat i on 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 ore representative but not necessarily maximum values. 4.0 ACTIVITIES Routine inspections were conducted during this report period. No other significant activities occurred at VBWR. Page 1 of 2 VBWR Annual Report No. 52 5.0 ORGANIZATION The organizational structure rema i ned unchanged during 2016. However, the Site Manager changed beginning in 2017. The Site Manager for 2016 wasT. A. Caine. The new Site Manager for 2017 isM. J. Feyrer. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS remains T. M. Leik_
 
==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 administrat i vely 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 '3fu{1Pii-Manager Vallecitos Nuclear Center Page 2 of 2 SURVEYOR (print and sign) I REVIEWER NO. 8 HITACHI Name and signatures on Original at GEH Vallecitos D-079 LOCATION DATE: VALLECITOS NUCLEAR CENTER 11/02/16 NUCLEAR SAFETY SURVEY RECORD VBWR Containment TIME: 1000 fBI Routine REASON D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS nem p T n TOTAL Dis lance liT JIT a a PT liT u a No. mRadlh mR/h mRemlh mRemlh CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Main Floor -General Area <0.5 <0.5 F <100 <500 <20 <200 IOOcm 2 -Area Over Reactor Vessel <0.5 <0.5 F <100 <500 <20 <200 lOOcm 3 4 Basement -General Area <1-1.5 <1-1.5 F <100 <500 <20 <200 IOOcm 5 -Sump 2 5 7 c <100 <500 <20 <200 IOOcm 6 7 Reactor Vessel Head Area <I <I F <100 <500 <20 <200 100cm 8 9 Top of Fuel Pool <0.5 <0.5 F <100 <500 <20 <200 IOOcm 10 11 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOcm 12 13 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOcm 14 15 16 INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM* E -120 RM-RM* PAC-1SA LUDLUM-12 SERIAL NUMBER 286 5057 897 Area Posted: (drcle applicable)
RA HRA CA RMA AIRBORNE PROBE a AC-JA (U) 10% X PROBE py PANCAKE 20% X p>MMENTS EFF a 43*4 (U) 10% EFF. (4P (4P GEO.) GEO.) NEO 289 (REV. 07/10)
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2016 Initial 1 Hour Decay 24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (mil ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCI/ml ncpm uCI/ml VBWR First Floor 2.83E+06 941.80 4.57E-10 2586.10 1.31E-09 445.00 2.16E-10 1042.10 5.06E-10 0.60 2.91E-13 3.50 1.77E-12 Basement 2.83E+06 1358.80 6.60E-10 3799.70 1.92E-09 628.80 3.05E-10 1469.90 7.14E-10 1.10 5.34E-13 13.70 6.92E-12 Fuel Pool 2.83E+06 1198.60 5.82E-10 3325.80 1.68E-09 443.40 2.15E-10 1015.40 4.93E-10 1.20 5.83E-13 5.40 2.73E-12 EVESR First Floor 2.83E+06 5419.80 2.63E-09 14593.00 7.37E-09 3220.50 1.56E-09 7528.90 3.66E-09 1.00 4.86E-13 5.10 2.58E-12 Basement 2.83E+06 10170.30 4.94E-09 27678.00 1.40E-08 1806.10 8.77E-10 3816.70 1.85E-09 2.70 1.31E-12 58.90 2.98E-11 519' Level 2.83E+06 6511.50 3.16E-09 18400.70 9.30E-09 927.20 4.50E-10 2005.50 9.74E-10 1.70 8.25E-13 13.40 6.77E-12 GETR First Floor 2.83E+06 203.80 9.90E-11 573.60 2.90E-10 71.90 3.49E-11 170.30 8.27E-11 0.80 3.88E-13 10.10 5.10E-12 Basement 2.83E+06 138.80 6.74E-11 350.40 1.77E*10 35.90 1.74E-11 92.20 4.48E*ll 0.90 4.37E-13 10.10 5.10E-12 Third Floor 2.83E+06 140.20 6.81E-11 424.40 2.14E-10 46.80 2.27E-ll 189.50 9.20E-11 1.00 4.86E-13 90.30 4.56E-11 Tennelec System "B" Efficiency
& Conversion Factors Alpha Efficiency 32.76% Beta Efficiency 31.49% dpm/uCI 2.22E+06 Alpha cpm/uCI 7.27E+05 Beta cpm/uCi 6.99E+OS Sampling Information Flow Minutes .8!!!. Total Total Samele Reactor Location Date Sameled Time On Time Off sameled (cfm) Flow (ft 3} ml/ft 3 VolumefmU VBWR First Floor 11/1/2016 10:30 10:50 20 5 100.0 28317 2.83E+06 VBWR Basement 11/2/2016 10:07 10:27 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/2/2016 9:45 10:05 20 5 100.0 28317 2.83E+06 EVESR First Floor 11/1/2016 9:00 9: 20 20 5 100.0 28317 2.83E+06 EVESR Basement 11/2/2016 12:58 13:18 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/2/2016 12:35 12:55 20 5 100.0 28317 2.83E+06 GETR First Floor 11/2/2016 14:13 14:33 20 5 100.0 28317 2.83E+06 GETR Basement 11/2/2016 14:36 14:56 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/2/2016 15:00 15:20 20 5 100.0 28317 2.83E+06
* HITACHI ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 49 FOR THE YEAR 2016 LICENSE DR-10 DOCKET 50-183 MARCH 2017 Vallecilcs Nuclear Center Sunol. Cabforrna EVESR Annual Report No. 49 ESADA-Vallecitos Experimental Superheat Reactor (Deactivated)
ANNUAL REPORT NO. 49 GE Hitachi Nuclear Energy IGEHl has maintained the ESADA Vallecitos Experimental Superheat Reactor (EVESRI 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. 2016 to December 31, 2016 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 mode for routine radiation surveys and o 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. 4.0 ACTIVITIES Routine inspections were conducted during this report period. The equipment disposal concluded during 2010. Page 1 of 2 EVESR Annual Report No. 49 5.0 ORGANIZATION The organizational structure remained unchanged during 2016. However, the Site Manager changed beginning in 2017. The Site Manager for 2016 wasT. A. Caine. The new Site Manager for 2017 isM. J. Feyrer. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS remains T. M. Leik.
 
==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 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 2 of 2 SURVEYOR (print and sign) I REVIEWER NO. 8 HITACHI Name and signatures on Original at GEH Vallecitos D-080 LOCATION DATE: VALLECITOS NUCLEAR CENTER 11/02/16 NUCLEAR SAFETY SURVEY RECORD EVESR Containment TIME: 0900 IE] Routine REASON [J Spedal Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item Jl y n TOTAL Distance Jly Jly a a JIY IIY u a No. mRadlh mR/h mRemlh mR11m/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Top of Spent Fuel Pool (Main Floorl <0.5 <0.5 F <100 <500 <20 <200 100cm 2 3 487' Level (Bosementl
<0.5 <0.5 F 150 750 <20 <200 lOOcm 4 503'Level
<1 <1 F <100 <500 <20 <200 lOOcm 5 519' Level <0.5 <0.5 c 100 500 <20 <200 lOOcm 6 534' Level -General Area <1 <I c 400 2000 <20 <200 lOOcm 7 -Floor Drain 7 7 c 8 -Emergency Cooling Valves 4.5 4.5 c 9 549' Level <0.5 <0.5 F <100 <500 <20 <200 tOO em 10 11 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 tOO em 12 Personnel Air lock <0.5 <0.5 F <100 <500 <20 <200 100cm 13 14 15 16 INSTRUMENT USED PRM-7 CP-S R0-20 PNR-4 TBM-E -120 RM-RM-PAC-1SA LUDLUM-12 SERIAl NUMBER 286 5057 897 Area Posted: (circle applicable)
RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE py PANCAKE 20% X COWAENtS a 43-4 (U) 10% EFF. EFF. (4P (4P GEO) GEO) NEO 289 (REV. 07110)
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2016 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 uO/ml VBWR First Floor 2.83E+06 941.80 4.57E-10 2586.10 1.31E-09 445.00 2.16E-10 1042.10 5.06E-10 0.60 2.91E-13 3.50 1.77E-12 Basement 2.83E+06 1358.80 6.60E-10 3799.70 1.92E-09 628.80 3.05E-10 1469.90 7.14E-10 1.10 5.34E-13 13.70 6.92E-12 Fuel Pool 2.83E+06 1198.60 5.82E-10 3325.80 1.68E-09 443.40 2.15E-10 1015.40 4.93E-10 1.20 5.83E-13 5.40 2.73E-12 EVESR First Floor 2.83E+06 5419.80 2.63E-09 14593.00 7.37E-09 3220.50 1.56E-09 7528.90 3.66E-09 1.00 4.86E-13 5.10 2.58E-12 Basement 2.83E+06 10170.30 4.94E-09 27678.00 1.40E-08 1806.10 8.77E-10 3816.70 1.85E-09 2.70 1.31E-12 58.90 2.98E-l1 519' Level 2.83E+06 6511.50 3.16E-09 18400.70 9.30E-09 927.20 4.50E-10 2005.50 9.74E-10 1.70 8.25E-13 13.40 6.77E-12 GETR First Floor 2.83E+06 203.80 9.90E-11 573.60 2.90E-10 71.90 3.49E-11 170.30 8.27E-11 0.80 3.88E-13 10.10 5.10E-12 Basement 2.83E+06 138.80 6.74E-11 350.40 1.77E-10 35.90 1.74E-11 92.20 4.48E-11 0.90 4.37E-13 10.10 5.10E-12 Third Floor 2.83E+06 140.20 6.81E-11 424.40 2.14E-10 46.80 2.27E-l1 189.50 9.20E-11 1.00 4.86E-13 90.30 4.56E-11 Tennelec System "B" Efficiency
& Conversion Factors Alpha Efficiency 32.76% Beta Efficiency 31.49% dpm/uCi 2.22E+06 Alpha cpm/uCI 7.27E+05 Beta cpm/uCi 6.99E+05 Sampling Information Flow Minutes Rate Total Total Sample Reactor Location Date Sampled Time On Time Off sampled (dml Flow(ft 3 l ml/ft 3 Volume(ml)
VBWR First Floor 11/1/2016 10:30 10:50 20 5 100.0 28317 2.83E+06 VBWR Basement 11/2/2016 10:07 10:27 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/2/2016 9:45 10:05 20 5 100.0 28317 2.83E+06 EVESR First Floor 11/1/2016 9:00 9:20 20 5 100.0 28317 2.83E+06 EVESR Basement 11/2/2016 12:58 13:18 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/2/2016 12:35 12:55 20 5 100.0 28317 2.83E+06 GETR First Floor 11/2/2016 14:13 14:33 20 5 100.0 28317 2.83E+06 GETR Basement 11/2/2016 14:36 14:56 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/2/2016 15:00 15:20 20 5 100.0 28317 2.83E+06
* HITACHI GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 58 FOR THE YEAR 2016 LICENSE TR-1 DOCKET 50-70 MARCH 2017 Volleotos Nuclear Center Sunol. Coliforma GETR Annual Report No. 58 General Electric Test Reactor (Deactivated)
ANNUAL REPORT NO. 58 GE Hitachi IGEH) has maintained the General Electric Test Reactor IGETRI 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. 2016 to December 31, 2016 is presented.
l.OSUMMARV 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 o general examination of conditions throughout the building.
The crone, elevator, and ventilation were serviced and tested in 2011 in anticipation of beginning remediation activities.
Such activities hove 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 10CFR50.59Iol in 2015. 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 ore presented in attachment
: 2. The radiation/contamination levels listed ore representative but not necessarily maximum values. The data below are from sample and dosimeter results accumulated during 2016. 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. 58 3.1 GETR Stack Although maintenance was performed an the stock in 2011, and the stack was tested, there has been no remediation effort performed for the GETR reactor. The ventilation system was operational from January 2016 until the end of November 2016. Alpha Concentration 7.14 x 1Q-16 )1Ci/cc Beta Concentration 1.94 x 10*1 4 J!Ci/cc 3.2 Air Monitors (Yearly overage of all meteorological stations.!
Four environmental air-monitoring stations ore positioned approximately 90 degrees apart around the operating facilities of the site. Each station is equipped with a membrane filter that is changed weekly and analyzed for gross alpha and gross beta-gamma.
Alpha Concentration:
Weekly Maximum. Weekly Average, Beta Concentration:
Weekly Maximum. Weekly Average, 3.3 Gamma Radiation 1.27 X 10*1 4 )1Ci/cc 1.35 x 10*15 J!Ci/cc 1.45 x 10-n J!Ci/cc 1.76 x 10*1 4 J!Ci/cc The yearly dose results for the year 2016 as determined from evaluation of site perimeter environmental monitoring dosimeters showed no departure from normal stable backgrounds.
 
===3.4 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. 3.5 GETR Well Analytical results of groundwater samples collected from the B-2 (GETR) well during the reporting period. Month Gross beta 11Ci/mL I Gross Alpha 11Ci/mL I Tritium 11Ci/mL June 2016 4.5Be-07 I 1.51E-07 I <MDC December 2016 Sample was lost Page 2 of 3 GETR Annual Report No. 58 4.0 ACTIVIT! ES 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 orgonizotionol structure remained unchanged during 2016. However, the Site Manager changed beginning in 2017. The Site Manager for 2016 wasT. A. Caine. The new Site Manager for 2017 is M. J. Feyrer. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS remains T. M. Leik.
 
==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 of3 SURVEYOR (print and sign) I REVIEWER NO. 8 HITACHI Name and signatures on Original at GEH Vallecitos C-032 LOCATION DATE: VALLECITOS NUCLEAR CENTER 11/02/16 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page I of 2) TIME: 1300 IE) Routine REASON D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS II em II ' n TOTAL [)jstance
"' liT 0 0 jly Pr u 0 No mRadlh mR/h mRemlh mRemlh CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOcm 2 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOcm 3 Personnel Air Lock SOP <100 <500 <20 <200 IOOcm 4 1st Floor -Clean Area * <0.5 <0.5 F <100 <500 <20 <200 IOOcm 5 -Zone Area* <1-7 <1-7 F 700 3500 <20 <200 IOOcm 6 2nd Floor -General Dose Rote <1-2 <1-2 F 7 -EEHS Cubicle Door 7 7 c 8 -Field Reading Around EEHS Cubicle 1.5-5 1.5-5 F 9 -Floor Smear I Clean Area * <100 <500 <20 <200 IOOcm 10 -Filter Bank <I <I c 11 Jrd Floor
* Zone Area North I Floor * <1-3 <1-3 F 1400 7000 <20 <200 IOOcm 12 -Zone Area South <I <I F 300 1500 <20 <200 IOOcm 13 -Bridge I Conal I 1 F <100 <500 <20 <200 100cm 14 -Missile Shield Point A * <1 <I F <100 <500 <20 <200 IOOcm 15 -Platform
<I <I F <100 <500 <20 <200 IOOcm 16 -Clean Area * <0.5 <0.5 F <100 <500 <20 <200 IOOcm INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM-E-120 RM* RM-PAC*15A LUDLUM-12 SERIAL NUMBER 286 5057 897 Area Posted: (circle applicable)
RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 1 0% X PROBE fl y PANCAKE 20% X OMI.ENTS
* Whatman Smears EFF. a 43-4 (U) 10% EFF. (4P (4P GEO) GEO) NEO 289 (REV. 07/10)
SURVEYOR (print and sign) I REVIEWER NO. 8 HITACHI Name and signatures on Original at GEH Vallecitos C-032 LOCATION DATE: VALLECITOS NUCLEAR CENTER 11/02/16 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of2) TIME: 1300 liD Routine REASON D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS nem ll T n TOTAL Distance liT fly d d fly fly u a No. mRadlh mRIIt mRemlh mRemlh CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 3rd Floor-Zone Area Floor Drain 40 s 45 c 2 Elevator <0.5 <0.5 F <100 <500 <20 <200 IOOcm 3 Basement -Clean Area * <1-3 <1-3 F <100 <500 <20 <200 100cm 4 -Filter Bonk <I <1 F 5 -ZoneAreo
* <1-7 <1-7 F 200 1000 <20 <200 IOOcm 6 -Control Rod Storage 50 50 c 7 -Control Rod Repair Hood 3 3 c 8 -Autoclave I Rod Work Areo <I <I c 9 Mezzanine between znd & 3'd Floors <O.S <O.S F <100 <SOO <20 <200 lOOcm 10 11 12 13 14 15 16 INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM* E-120 RM* RM-PAC*1SA LUDLUM-12 SERIAL NUMBER 286 5057 897 Area Posted: (circle applicable)
RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE fly PANCAKE 20% X 5
* Whotman Smears EFF. a 43-4 (U) 10% EFF. ** Gamma Spectroscopy indicates this is Cs-13 7 (4P (4P GEO .* GEO.) NEO 289 (REV. 07/10)
ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2016 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+06 941.80 4.57E-10 2586.10 1.31E-09 445.00 2.16E-10 1042.10 5.06E-10 0.60 2.91E-13 3.50 1.77E-12 Basement 2.83E+06 1358.80 6.60E-10 3799.70 1.92E-09 628.80 3.05E-10 1469.90 7.14E-10 1.10 5.34E-13 13.70 6.92E-12 Fuel Pool 2.83E+06 1198.60 5.82E-10 3325.80 1.68E-09 443.40 2.15E-10 1015.40 4.93E-10 1.20 5.83E-13 5.40 2.73E-12 EVESR First Floor 2.83E+06 5419.80 2.63E-09 14593.00 7.37E-09 3220.50 1.56E-09 7528.90 3.66E-09 1.00 4.86E-13 5.10 2.58E-12 Basement 2.83E+06 10170.30 4.94E-09 27678.00 1.40E-08 1806.10 8.77E-10 3816.70 1.85E-09 2.70 1.31&#xa3;-12 58.90 2.98E-ll 519' Level 2.83E+06 6511.50 3.16E-09 18400.70 9.30E-09 927.20 4.50E-10 2005.50 9.74E-10 1.70 8.25E-13 13.40 6.77E-12 GETR First Floor 2.83E+06 203.80 9.90E-11 573.60 2.90E-10 71.90 3.49E-11 170.30 8.27E-ll 0.80 3.88E-13 10.10 5.10E-12 Basement 2.83E+06 138.80 6.74E-ll 350.40 1.77E-10 35.90 1.74E-11 92.20 4.48E-ll 0.90 4.37E-13 10.10 5.10E-12 Third Floor 2.83E+06 140.20 6.81E-11 424.40 2.14E-10 46.80 2.27E-11 189.50 9.20E-11 1.00 4.86E-13 90.30 4.56E-11 Tennelec System "B" Efficiency
& Conversion Factors Alpha Efficiency 32.76% Beta Efficiency 31.49% dpm/uCI 2.22E+06 Alpha cpm/uCi 7.27E+05 Beta cpm/uCI 6.99E+OS Sampling Information
!liD!. Minutes Rate Total Total Samele Reactor Location Date Sampled nmeOn nmeoff sampled (dm) Flow ml/ft 3 Volume_lmll VBWR First Floor 11/1/2016 10:30 10:50 20 5 100.0 28317 2.83E+06 VBWR Basement 11/2/2016 10:07 10:27 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/2/2016 9:45 10:05 20 5 100.0 28317 2.83E+06 EVE5R First Floor 11/1/2016 9:00 9:20 20 5 100.0 28317 2.83E+06 EVESR Basement 11/2/2016 12:58 13:18 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/2/2016 12:35 12:55 20 5 100.0 28317 2.83E+06 GETR First Floor 11/2/2016 14:13 14:33 20 5 100.0 28317 2.83E+06 GETR Basement 11/2/2016 14:36 14:56 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/2/2016 15:00 15:20 20 5 100.0 28317 2.83E+06}}

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