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=Text=
=Text=
{{#Wiki_filter:HITACHI VALLECITOS BOILING WATER REACTOR (DEACTIVATED)
{{#Wiki_filter:HITACHI Vallecitos Nuclear Center Sunol, California VALLECITOS BOILING WATER REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 50 FOR THE VEAR 2014 LICENSE DPR-1 DOCKET 50-18 MARCH 2015 Vallecitos Nuclear Center Sunol, California HITACHI Vallecitos Boiling Water Reactor (Deactivated)
ANNUAL REPORT NO. 50 FOR THE VEAR 2014 LICENSE DPR-1 DOCKET 50-18 MARCH 2015
Annual Report No. 50 Vallecitos Nuclear Center Sunol, California 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. 2014 to December 31, 2014 is presented, as required by paragraph S.d.2 of the license. 1.0 SUMMARV 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 FACILITV 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 law. Results of the surveys are presented in attachment  
 
: 1. Air sampling results are presented in attachment  
HITACHI Vallecitos Nuclear Center Sunol, California Vallecitos Boiling Water Reactor (Deactivated)
: 2. The radiation/contamination levels listed are representative but not necessarily maximum values. 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 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS remains E. F. Saito. In early 2015, prior to issuance of this report, the Manager, Regulatory Compliance and EHS changed toT. M. Leik.  
Annual Report No. 50 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. 2014 to December 31, 2014 is presented, as required by paragraph S.d.2 of the license.
1.0 SUMMARV 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 FACILITV 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 law.
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. No other significant activities
 
occurred at VBWR.
5.0 ORGANIZATION The organizational structure remained unchanged during 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS remains E. F. Saito.
In early 2015, prior to issuance of this report, the Manager, Regulatory Compliance and EHS changed toT. M. Leik.


==6.0 CONCLUSION==
==6.0 CONCLUSION==


GE Hitachi Nuclear Energy concludes that the deactivated VBWR is being maintained in a safe shutdown condition.
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.
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 T. A. Caine Manager Vallecitos Nuclear Center
GE Hitachi Nuclear Energy Vallecitos Operations T. A. Caine Manager Vallecitos Nuclear Center ATTACHMENT 1 SURVEYOR (print and sign) I REVIEWER NO. HITACHI Name and signatures on Original at GEH Vallecitos D-092 LOCATION DATE: VALLECITOS NUCLEAR CENTER 12/12/14 NUCLEAR SAFETY SURVEY RECORD VBWR Containment TIME: 1000 lXI Routine rEASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item p y !l TOTAL Distance fly flY a a llr f.ly a Q No. mRad/h mRJh mRam/h mR.emlh CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Main Floor -General Area <0.5 <0.5 F <100 <500 <20 <200 lOOcm 2 -Area Over Reactor Vessel <0.5 <0.5 F <100 <500 <20 <200 lOOcm 3 L 4 Basement -General Area <0.5 -1 <0.5. 1 F <100 <500 <20 <200 100 em 5 -Sump 5 4 9 c 200 1000 <20 <200 lOOcm 6 7 Reactor Vessel Head Area <1 <1 F <100 <500 <20 <200 lOOcm 8 9 Top of Fuel Pool <0.5 <0.5 F <100 <500 <20 <200 100cm 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 lOOcm 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 1339 897 Area Posted: (circle appHcable)
 
RA HRA CA RMA AIRBORNE PROSE a AC -3A {U) 10% X PROBE )ly PANCAKE 20% X OMUENTS a 43-4 (U) 10% EFF. EFF. (4 p (4 p GEO.) GEO.) NEO 289 (REV. 0711 0}
ATTACHMENT 1 SURVEYOR (print and sign)                   IREVIEWER                      NO.
ATTACHMENT 2: Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial At Samgling Time Sample Alpha Beta Alpha Beta Reactor Location Volume(ml) ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 427.91 1.97E-10 1074.67 4.98E-10 892.2432 4.11&#xa3;-10 2240.815 1.04E-09 Basement 2.83&#xa3;+06 1324.41 6.10E-10 3298.66 1.53E-09 2460.261 1.13E-09 6127.683 2.84E-09 Fuel Pool 2.83&#xa3;+06 1048.93 4.83&#xa3;-10 2660.80 1.23E-09 1948.522 8.97E-10 4942.776 2.29E-Q9 EVESR First Floor 2.83E+06 1292.39 5.95E-10 3428.86 1.59E-09 2400.78 l.llE-09 6369.546 2.95E-09 Basement 2.83E+06 1066.39 4.91E-10 2858.58 1.33&#xa3;-09 2223.55 1.02E-09 5960.479 2.76E-09 519'level 2.83E+06 1037.91 4.78E-10 2771.47 1.29E-09 2164.166 9.96E-10 5778.844 2.68E-09 GETR first Floor 2.83E+06 86.66 3.99E-11 219.20 1.02E-10 160.982 7.41E-11 407.192 1.89E-10 Basement 2.83E+06 93.06 4.28E-11 237.77 l.lOE-10 172.8708 7.96E-11 441.6882 2.05E-10 Third Floor 2.83E+06 175.52 8.08E-11 445.04 2.06E-10 326.0508 1.SOE-10 826.7187 3.83E-10 Tennelec System "A" Efficiency  
Name and signatures on Original at GEH Vallecitos                             D-092 HITACHI                          LOCATION                                                                   DATE:
& Conversion Factors Alpha Efficiency 34.58% Beta Efficiency 34.32% dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Radon Decay Factors Samolina Minutes I.!.m!L Time Decay Decav Minutes Time Reactor Location Date Sameled Time On Time Off sameled Factor Counted Time Factor Counted Factor Radon Desay Factor VBWR First Floor 12/12/2014 10:55 11:20 25 1.316463 11:35 15 1.414216 10 1.11997 2.08511875 VBWR Basement 12/12/2014 10:25 10:50 25 1.316463 11:00 10 1.259922 10 1.11997 1.85762782 VBWR Fuel Pool 12/12/2014 9:55 10:20 25 1.316463 10:30 10 1.259922 10 1.11997 1.85762782 EVESR First Floor 12/12/2014 11:45 12:10 25 1.316463 12:20 10 1.259922 10 1.11997 1.85762782 EVESR Basement 12/12/2014 12:40 13:05 25 1.316463 13:20 15 1.414216 10 1.11997 2.08511875 EVESR 519' level 12/12/2014 12:10 12:35 25 1.316463 12:50 15 1.414216 10 1.11997 2.08511875 GETR First Floor 12/12/2014 15:30 15:55 25 1.316463 16:05 10 1.259922 10 1.11997 1.85762782 GETR Basement 12/12/2014 16:00 16:25 25 1.316463 16:35 10 1.259922 10 1.11997 1.85762782 GETR Third Floor 12/12/2014 17:00 17:25 25 1.316463 17:35 10 1.259922 10 1.11997 1.85762782 HITACHI ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)
VALLECITOS NUCLEAR CENTER                                                                                                             12/12/14 TIME:
ANNUAL REPORT NO. 47 FOR THE VEAR 2014 LICENSE DR-10 DOCKET 50-183 MARCH 2015 Vallecitos Nuclear Center Sunol. California ESADA-Vallecitos EMperimental Superheat Reactor (Deactivated)
NUCLEAR SAFETY SURVEY RECORD                                     VBWR Containment                                                             1000 lXI Routine rEASON 0 Special               Annual Survey ITEMS OR LOCATION                           DOSE RATE                       DIRECT READING                   SMEAR READINGS Item                                             p       y       !l     TOTAL Distance fly     flY     a       a     llr       f.ly     a     Q No.                                           mRad/h   mRJh   mRam/h mR.emlh         CPM     dPM     CPM     dPM   CPM       dPM       CPM   dPM   AREA 1 Main Floor - General Area                           <0.5             <0.5     F                                   <100       <500       <20   <200 lOOcm 2   - Area Over Reactor Vessel                       <0.5             <0.5     F                                   <100       <500       <20   <200 lOOcm 3
ANNUAL REPORT NO. 47 GE Hitachi Nuclear Energy (GEH) has maintained the ESADA Vallecitos Experimental Superheat Reactor (EVESRl 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, 2014 to December 31. 2014 is presented.
4 Basement - General Area                           <0.5 -1           <0.5. 1     F                                   <100       <500 L<20     <200 100 em 5   -Sump                                     5       4                 9     c                                     200       1000       <20   <200 lOOcm 6
as required by Amendment 7, Appendix A. Technical Specifications, section C. 1. 1.0  
7 Reactor Vessel Head Area                             <1               <1       F                                   <100       <500       <20   <200 lOOcm 8
9 Top of Fuel Pool                                   <0.5             <0.5       F                                   <100       <500       <20   <200 100cm 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 lOOcm 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                                 1339                                 897 Area Posted: (circle appHcable) RA   HRA CA RMA   AIRBORNE                     PROSE   a AC -3A {U)         10%   X PROBE     )ly PANCAKE           20%   X OMUENTS EFF. a 43-4 (U)           10%       EFF.
(4 p                                 (4 p GEO.)                                 GEO.)
NEO 289 (REV. 0711 0}
 
ATTACHMENT 2:             Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial                             At Samgling Time Sample           Alpha                   Beta               Alpha               Beta Reactor     Location     Volume(ml)     ncpm     uCi/ml       ncpm       uCi/ml   ncpm     uCi/ml   ncpm     uCi/ml VBWR     First Floor       2.83E+06       427.91 1.97E-10     1074.67 4.98E-10 892.2432 4.11&#xa3;-10 2240.815       1.04E-09 Basement           2.83&#xa3;+06     1324.41 6.10E-10       3298.66 1.53E-09 2460.261 1.13E-09 6127.683       2.84E-09 Fuel Pool         2.83&#xa3;+06     1048.93 4.83&#xa3;-10       2660.80 1.23E-09 1948.522 8.97E-10 4942.776       2.29E-Q9 EVESR   First Floor       2.83E+06     1292.39 5.95E-10       3428.86 1.59E-09 2400.78 l.llE-09 6369.546         2.95E-09 Basement           2.83E+06     1066.39 4.91E-10       2858.58 1.33&#xa3;-09 2223.55 1.02E-09 5960.479         2.76E-09 519'level         2.83E+06     1037.91 4.78E-10       2771.47 1.29E-09 2164.166 9.96E-10 5778.844       2.68E-09 GETR     first Floor       2.83E+06       86.66 3.99E-11       219.20 1.02E-10 160.982 7.41E-11 407.192         1.89E-10 Basement           2.83E+06       93.06 4.28E-11       237.77 l.lOE-10 172.8708 7.96E-11 441.6882     2.05E-10 Third Floor       2.83E+06     175.52 8.08E-11         445.04 2.06E-10 326.0508 1.SOE-10 826.7187     3.83E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency       34.58%
Beta Efficiency       34.32%
dpm/uCi       2.22E+06 Alpha cpm/uCi       7.68E+05 Beta cpm/uCi       7.62E+05 Radon Decay Factors Samolina                                           ~
Minutes       I.!.m!L Time     Decay     Decav   Minutes     Time Reactor     Location     Date Sameled Time On Time Off sameled Factor Counted                 Time   Factor Counted       Factor Radon Desay Factor VBWR       First Floor   12/12/2014   10:55     11:20         25     1.316463 11:35         15   1.414216     10     1.11997   2.08511875 VBWR       Basement       12/12/2014   10:25     10:50         25     1.316463 11:00         10   1.259922     10     1.11997   1.85762782 VBWR       Fuel Pool     12/12/2014     9:55     10:20         25     1.316463 10:30         10   1.259922     10     1.11997   1.85762782 EVESR     First Floor   12/12/2014   11:45     12:10         25     1.316463   12:20       10   1.259922     10     1.11997   1.85762782 EVESR     Basement       12/12/2014   12:40     13:05         25     1.316463   13:20       15   1.414216     10     1.11997   2.08511875 EVESR     519' level     12/12/2014   12:10     12:35         25     1.316463   12:50       15   1.414216     10     1.11997   2.08511875 GETR     First Floor   12/12/2014   15:30     15:55         25     1.316463   16:05       10   1.259922     10     1.11997   1.85762782 GETR     Basement       12/12/2014   16:00     16:25         25     1.316463   16:35       10   1.259922     10     1.11997   1.85762782 GETR     Third Floor   12/12/2014   17:00     17:25         25     1.316463   17:35       10   1.259922       10     1.11997   1.85762782
 
HITACHI Vallecitos Nuclear Center Sunol. California ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 47 FOR THE VEAR 2014 LICENSE DR-10 DOCKET 50-183 MARCH 2015
 
ESADA-Vallecitos EMperimental Superheat Reactor (Deactivated)
ANNUAL REPORT NO. 47 GE Hitachi Nuclear Energy (GEH) has maintained the ESADA Vallecitos Experimental Superheat Reactor (EVESRl 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, 2014 to December 31. 2014 is presented. as required by Amendment 7, Appendix A. Technical Specifications, section C. 1.
1.0  


==SUMMARY==
==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 549level.
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 ore 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 of2 


===5.0 ORGANIZATION===
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 549level. 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 ore 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 of2


The organizational structure remained unchanged during 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R Schrag. The Manager, Regulatory Compliance and EHS remains E. F. Saito. In early 2015, prior to issuance of this report, the Manager. Regulatory Compliance and EHS changed to T. M. Leik.  
5.0 ORGANIZATION The organizational structure remained unchanged during 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R Schrag. The Manager, Regulatory Compliance and EHS remains E. F. Saito.
In early 2015, prior to issuance of this report, the Manager. Regulatory Compliance and EHS changed to T. M. Leik.


==6.0 CONCLUSION==
==6.0 CONCLUSION==


GE Hitachi Nuclear Energy concludes that the deactivated ESADA-Vallecitos Experimental Superheat Reactor is being maintained in a safe shutdown condition.
GE Hitachi Nuclear Energy concludes that the deactivated ESADA-Vallecitos Experimental Superheat Reactor is being maintained in a safe shutdown condition.
The inspections.
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.
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 T. A. Caine Manager Vallecitos Nuclear Center Page
GE Hitachi Nuclear Energy Vallecitos Operations T. A. Caine Manager Vallecitos Nuclear Center Page ATIACHMENTl SURVEYOR (print and sign) !REVIEWER NO. HITACHI Name and signatures on Original at GEH Vallecitos D-093 LOCATION DATE: VALLECITOS NUCLEAR CENTER 12/12/14 NUCLEAR SAFETY SURVEY RECORD EVESR Containment TIME: 1200 IRI Routine REASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item p y n TOTAL Distance Jly llr (1 (I ll1 a. " No. mRadlh mFUh mRemlh mRemlh 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 IOOcm 2 3 487' Level {Basement)  
 
<1 <i F 100 500 <20 <200 lOOcm 4 503'Level  
ATIACHMENTl SURVEYOR (print and sign)                   !REVIEWER                       NO.
<0.5 <0.5 F 5 519' level <0.5 <0.5 c 150 750 <20 < lOOcm 6 534' Level -General Area <1 <I c 150 750 <20 <200 lOOcm 7 -Floor Drain <0.5 I <0.5 F 8 -Emergency Cooling Valves 4 4 c 9 549' level <0.5 <0.5 F <100 <500 <20 <200 lOOcm 10 11 Equipment Air Lock <0.5 <0.5 F <!00 <500 <20 <200 lOOcm 12 Personnel Air Lock <0.5 <0.5 F <100 <500 0 <200 lOOcm 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 285 1339 897 Area Posted: {circle applicable)
Name and signatures on Original at GEH Vallecitos                                 D-093 HITACHI                          LOCATION                                                                     DATE:
RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE ll'f PANCAKE 20% X COMMENTS a 43
VALLECITOS NUCLEAR CENTER                                                                                                               12/12/14 NUCLEAR SAFETY SURVEY RECORD                                       EVESR Containment                                                 TIME:
* 4 (U) 10% EFF. EFF. (4P {4P GEO./ GEO.) NEO 289 (REV. 07110)
1200 IRI Routine REASON 0   Special               Annual Survey ITEMS OR LOCATION                             DOSE RATE                         DIRECT READING                     SMEAR READINGS Item                                               p       y       n   TOTAL Distance Jly       llr     (1     (I ll1         ~y      a.
ATTACHMENT 2: Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial At Same ling Time Sample Alpha Reactor location Volume (ml) ncpm uO/ml VBWR First Floor 2.83E+06 427.91 1.97E-10 Basement 2.83E+06 1324.41 6.10&#xa3;-10 Fuel Pool 2.83E+06 1048.93 4.83&#xa3;-10 EVESR First Floor 2.83E+06 1292.39 5.95&#xa3;-10 Basement 2.83E+06 1066 .. 39 4.91E-10 519' Level 2.83E+06 1037.91 4.78E*10 GETR First Floor 2.83E+06 86.66 3.99E*l1 Basement 2.83E+06 93.06 4.28&#xa3;-11 Third Floor 2.83E+06 175.52 8.08E-11 Tennelec System "A" Efficiency
No.                                             mRadlh   mFUh     mRemlh mRemlh         CPM       dPM     CPM     dPM     CPM         dPM     CPM     "
& Conversion Factors Reactor VBWR VBWR VBWR EVESR EVESR EVESR GETR GETR GETR Alpha Efficiency 34.58% Beta Efficiency dpm/uCi Alpha cpm/uCi Betacpm/uO location First Floor Basement Fuel Pool First Floor Basement 519'Level First Floor Basement Third Floor 34.32% 2.22&#xa3;+06 7.68&#xa3;+05 7.61E+05 Date Samoled 12/12/2014 12/12/2014 12/12/2014 12/12/2014 12/12/2014 12/12/2014 12/12/2014 12/12/2014 12/12/2014 Time on Time off 10:55 11:20 10:25 10:50 9:55 10:20 11:45 12:10 12:40 13:05 12:10 12:35 15:30 15:55 16:00 16:25 17:00 17:25 Beta Alpha Beta ncpm uCi/ml ncpm uCi/ml !l9ml uCi/ml 1074.67 4.98&#xa3;-10 892.2432 4.11E-10 2240.815 1.04E-09 3298.66 1.53E-09 2460.261 1.13&#xa3;-09 6127.683 2.84E-09 2660.80 1.23E-09 1948.522 8.97&#xa3;-10 4942.776 2.29E-09 3428.86 1.59E-09 2400.78 l.llE-09 6369.546 2.95E-09 2858.58 1.33E-09 2223.55 1.02E-09 5960.479 2.76.&#xa3;-09 2771.47 1.29&#xa3;-09 2164.166 9.96E-10 5778.844 2.68E-09 219.20 1.02E-10 160.982 7.41E-ll 407.192 1.89E-10 237.77 1.10E-10 172.8708 7.96E-11 441.6882 2.05E-10 445.04 2.06E-10 326.0508 1.50E*10 826.7187 3.83E-10 Radon Decay Factors Samolin2 I!.m!l Time Decay Decay Minutes sameled Factor Counted Time Factor Counted 25 1.316463 11:35 15 1.414216 10 25 1.316463 11:00 10 1.259922 10 25 1.316463 10:30 10 1.259922 10 25 1.316463 12:20 10 1.259922 10 25 1.316463 13:20 15 1.414216 10 25 1.316463 12:50 15 1.414216 10 25 1.316463 16:05 10 1.259922 10 25 1.316463 16:35 10 1.259922 10 25 1.316463 17:35 10 1.259922 10 Time Factor Radon 1.11997 2.08511875 1.11997 1.85762782 1.11997 1.85762782 1.11997 1.85762782 1.11997 2.08511875 1.11997 2.08511875 1.11997 1.85762782 1.11997 1.85762782 1.11997 1.85762782 HITACHI GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)
dPM   AREA 1 Top of Spent Fuel Pool {Main Floorl                 <0.5             <0.5     F                                       <100       <500     <20   <200 IOOcm 2
ANNUAL REPORT NO. 56 FOR THE VEAR 2014 LICENSE TR-1 DOCKET 50-70 MARCH 2015 Vallecitos Nuclear Center Sunol, California GETR Annual Report No. 56 General Electric Test Reactor (Deactivated)
3 487' Level {Basement)                                 <1               <i     F                                         100         500     <20   <200 lOOcm 4 503'Level                                           <0.5             <0.5     F 5 519' level                                           <0.5             <0.5     c                                       150         750     <20   <     lOOcm 6 534' Level -General Area                             <1               <I     c                                       150         750     <20   <200 lOOcm 7   - Floor Drain                                     <0.5   I         <0.5     F 8   - Emergency Cooling Valves                           4               4       c 9 549' level                                           <0.5             <0.5     F                                       <100       <500     <20   <200 lOOcm 10 11 Equipment Air Lock                                   <0.5             <0.5     F                                       <!00       <500     <20   <200 lOOcm 12 Personnel Air Lock                                 <0.5             <0.5     F                                       <100       <500       0   <200 lOOcm 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                                           285                               1339                                     897 Area Posted: {circle applicable) RA   HRA CA RMA   AIRBORNE                     PROBE   a AC- 3A (U)           10%     X PROBE     ll'f PANCAKE         20%   X COMMENTS EFF. a 43
* 4 (U)           10%       EFF.
(4P                                       {4P GEO./                                     GEO.)
NEO 289 (REV. 07110)
 
ATTACHMENT 2:             Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial                             At Same ling Time Sample           Alpha                  Beta              Alpha               Beta Reactor     location     Volume (ml)   ncpm     uO/ml        ncpm      uCi/ml    ncpm    uCi/ml    !l9ml    uCi/ml VBWR     First Floor         2.83E+06     427.91 1.97E-10     1074.67 4.98&#xa3;-10 892.2432 4.11E-10 2240.815        1.04E-09 Basement           2.83E+06     1324.41 6.10&#xa3;-10       3298.66 1.53E-09 2460.261 1.13&#xa3;-09 6127.683       2.84E-09 Fuel Pool          2.83E+06    1048.93 4.83&#xa3;-10      2660.80 1.23E-09 1948.522 8.97&#xa3;-10 4942.776       2.29E-09 EVESR    First Floor        2.83E+06    1292.39 5.95&#xa3;-10      3428.86 1.59E-09 2400.78 l.llE-09 6369.546         2.95E-09 Basement          2.83E+06    1066..39 4.91E-10      2858.58 1.33E-09 2223.55 1.02E-09 5960.479         2.76.&#xa3;-09 519' Level        2.83E+06    1037.91 4.78E*10      2771.47 1.29&#xa3;-09 2164.166 9.96E-10 5778.844       2.68E-09 GETR    First Floor        2.83E+06        86.66 3.99E*l1        219.20 1.02E-10 160.982 7.41E-ll 407.192         1.89E-10 Basement          2.83E+06        93.06 4.28&#xa3;-11        237.77 1.10E-10 172.8708 7.96E-11 441.6882       2.05E-10 Third Floor        2.83E+06      175.52 8.08E-11        445.04 2.06E-10 326.0508 1.50E*10 826.7187       3.83E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency        34.58%
Beta Efficiency        34.32%
dpm/uCi      2.22&#xa3;+06 Alpha cpm/uCi        7.68&#xa3;+05 Betacpm/uO        7.61E+05 Radon Decay Factors Samolin2                                             ~
Minut~s      I!.m!l   Time     Decay     Decay   Minutes     Time Reactor      location    Date Samoled Time on Time off sameled           Factor Counted   Time     Factor   Counted     Factor Radon De~
VBWR      First Floor    12/12/2014    10:55      11:20        25     1.316463   11:35       15   1.414216       10     1.11997    2.08511875 VBWR      Basement      12/12/2014    10:25      10:50        25     1.316463   11:00       10   1.259922       10      1.11997    1.85762782 VBWR      Fuel Pool      12/12/2014    9:55      10:20        25     1.316463   10:30       10   1.259922       10     1.11997    1.85762782 EVESR      First Floor    12/12/2014    11:45      12:10        25     1.316463   12:20       10   1.259922       10     1.11997    1.85762782 EVESR      Basement      12/12/2014    12:40      13:05        25     1.316463   13:20       15   1.414216       10      1.11997    2.08511875 EVESR      519'Level      12/12/2014    12:10     12:35        25     1.316463   12:50       15   1.414216       10     1.11997    2.08511875 GETR      First Floor    12/12/2014    15:30      15:55        25     1.316463   16:05       10   1.259922       10     1.11997    1.85762782 GETR      Basement      12/12/2014    16:00      16:25         25    1.316463   16:35       10   1.259922       10     1.11997   1.85762782 GETR      Third Floor    12/12/2014    17:00      17:25        25    1.316463  17:35      10    1.259922      10      1.11997   1.85762782
 
HITACHI Vallecitos Nuclear Center Sunol, California GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 56 FOR THE VEAR 2014 LICENSE TR-1 DOCKET 50-70 MARCH 2015
 
GETR Annual Report No. 56 General Electric Test Reactor (Deactivated)
ANNUAL REPORT NO. 56 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. ln this annual report, a summary of the status of the facility for the period of January 1, 2014 to December 31. 2014 is presented.
ANNUAL REPORT NO. 56 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. ln this annual report, a summary of the status of the facility for the period of January 1, 2014 to December 31. 2014 is presented.
1.0  
1.0  


==SUMMARY==
==SUMMARY==
The facility remains in essentially the same condition described in Annual Report No. 55. 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.
The facility remains in essentially the same condition described in Annual Report No. 55. 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.
Such activities have not begun. 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. There were no changes authorized by the Facility Manager pursuant to 10CFR50.59!al in 2014. 3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low. Results of the surveys ore presented in attachment  
Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review.
: 1. Air sampling results are presented in attachment  
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!al in 2014.
: 2. The radiation/contamination levels listed are representative but not necessarily maximum values. 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 Page 1 2 stack air flow has been documented.
3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low. Results of the surveys ore presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.
Stack records are available on site far review. 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 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager. Regulatory Compliance and EHS remains E. F. Saito. In early 2015, prior to issuance of this report. the Manager, Regulatory Compliance and EHS changed toT. M. Leik.  
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 Page 1 2
 
stack air flow has been documented. Stack records are available on site far review.
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 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager.
Regulatory Compliance and EHS remains E. F. Saito.
In early 2015, prior to issuance of this report. the Manager, Regulatory Compliance and EHS changed toT. M. Leik.


==6.0 CONCLUSION==
==6.0 CONCLUSION==


GE Hitachi Nuclear Energy concludes that the deactivated GETR is being maintained in a safe shutdown condition.
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.
The inspections.
GE Hitachi Nuclear Energy Vallecitos Operations T.A. Caine Manager Vallecitos Nuclear Center
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 T.A. Caine Manager Vallecitos Nuclear Center ATTACHMENT 1 SURVEYOR (print and sign) I REVIEWER NO. HITACHI Name and signatures on Original at GEH Vallecitos C-027 LOCATION DATE: VALLECITOS NUCLEAR CENTER 12112114 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 1 of2) TIME: 1400 IRI Routine REASON D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item 13 y n TOTAL Distance jjy a* ()( 13Y py a a No. mRad/h mRih mRemlh mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 em 2 Eguipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 em 3 Personnel Air Lock SOP <100 <500 <20 <200 100 em 4 1st Floor -Clean Area * <0.5 <0.5 F <100 <500 <20 <200 100 em 5 -Zone Area* <1-3 <1-3 F 1600 8000 <20 <200 100 em 6 2nd Floor-General Dose Rate <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 <200 100 em 10 -Filter Bank <1 <1 c 11 3rd Floor-Zone Area North I Floor* <1-4 <1-4 F 800 4000 <20 <200 100em 12 -Zone Area South <0.5 <0.5 F <100 <500 <20 <200 100 em 13 -Bridge I Canal 1.5 1.5 F 300 1500 <20 <200 100em 14 -Missile Shield Point A* <1 <1 F <100 <500 <20 <200 100 em 15 -Platform  
ATTACHMENT 1 SURVEYOR (print and sign)                 IREVIEWER                      NO.
<0.5 <0.5 F 100 500 <20 <200 lOOem 16 -Clean Area * <0.5 <0.5 F <100 <500 <20 <200 100 em INSTRUMENT USED PRM-7 CP-5 RO -20 PNR-4 TBM-E-120 RM-RM-PAC -1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: (circle applicable)
Name and signatures on Original at GEH Vallecitos                             C-027 HITACHI                            LOCATION                                                                 DATE:
RA HRA CA RMA AIRBORNE PROBE o. AC-3A (U) 10% X PROBE PANCAKE 20% X COMMENTS
VALLECITOS NUCLEAR CENTER                                                                                                           12112114 TIME:
* Whatman Smears a 43-4 (U) 10% EFF. EFF. (4 p (4 p GEO.) GEO.) NEO 289 (REV. 07/10)
NUCLEAR SAFETY SURVEY RECORD                                       200 Area GETR Containment (page 1 of2)                                       1400 IRI Routine REASON D   Special               Annual Survey ITEMS OR LOCATION                             DOSE RATE                       DIRECT READING                   SMEAR READINGS Item                                                 13       y     n     TOTAL   Distance jjy     ~y      a*     ()(     13Y       py     a     a No.                                               mRad/h   mRih   mRemlh mRem/h           CPM     dPM     CPM     dPM     CPM       dPM     CPM   dPM   AREA 1 Personnel Air Lock                                     <0.5           <0.5       F                                   <100       <500     <20   <200 100 em 2 Eguipment Air Lock                                     <0.5           <0.5       F                                   <100       <500     <20   <200 100 em 3 Personnel Air Lock SOP                                                                                               <100       <500     <20   <200 100 em 4 1st Floor - Clean Area *                               <0.5           <0.5       F                                   <100       <500     <20   <200 100 em 5   -Zone Area*                                         <1-3           <1-3       F                                   1600     8000     <20   <200 100 em 6 2nd Floor- General Dose Rate                         <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   <200 100 em 10   -Filter Bank                                         <1             <1       c 11 3rd Floor- Zone Area North I Floor*                   <1-4           <1-4       F                                   800       4000     <20   <200 100em 12   -Zone Area South                                     <0.5           <0.5       F                                   <100       <500     <20   <200 100 em 13   - Bridge I Canal                                     1.5             1.5       F                                   300       1500     <20   <200 100em 14   -Missile Shield Point A*                             <1             <1       F                                   <100       <500     <20   <200 100 em 15   -Platform                                           <0.5           <0.5       F                                     100       500     <20   <200 lOOem 16   - Clean Area *                                       <0.5           <0.5       F                                   <100       <500     <20   <200 100 em INSTRUMENT USED                     PRM-7   CP-5       RO -20     PNR-4       TBM-       E- 120     RM-       RM-             PAC -1SA   LUDLUM-12 SERIAL NUMBER                                             285                                 1339                                 897 Area Posted: (circle applicable) RA HRA   CA RMA     AIRBORNE                     PROBE   o. AC- 3A (U)       10%     X PROBE     ~y  PANCAKE         20%   X COMMENTS
ATTACHMENT 1 SURVEYOR (print and sign) I REVIEWER NO. e HITACHI Name and signatures on Original at GEH Vallecitos C-027 LOCATION DATE: VALLECITOS NUCLEAR CENTER 12/12/14 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of2) TIME: 1400 liD Routine REASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item f3 y n TOTAL Distance f3y f3y a a f3y f3r a a No. mRad/h mRih mRemlh mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 3rd Floor-Zone Area Floor Drain 60 4 64 c 2 Elevator <0.5 <0.5 F <100 <500 <20 <200 lOOcm 3 Basement-Clean Area* <l-3 <1-3 F <100 <500 <20 <200 lOOcm 4 -Filter Bank I I F 5 -Zone Area* <1-5 <1-5 F 200 1000 <20 <200 100 em 6 -Control Rod Storage 1.0-50 1.0-50 c 7 -Control Rod Repair Hood <1-3 <1-3 F-C 8 -Autoclave I Rod Work Area <1 <1 c 9 Mezzanine between 2nd & 3rd Floors <0.5 <0.5 F <100 <500 <20 <200 100 em 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 285 1339 897 Area Posted: (circle applicable)
* Whatman Smears                                                       EFF. a 43-4 (U)         10%         EFF.
RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE (3y PANCAKE 20% X COMMENTS
(4 p                                   (4 p GEO.)                                 GEO.)
* Whatman Smears EFF. a 43-4 (U) 10% EFF. (4 p (4 p GEO.) GEO.) NEO 289 (REV. 07/10)
NEO 289 (REV. 07/10)
ATTACHMENT 2: Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial At Sameling Time Sample Alpha Beta Alpha Beta Reactor Location Volume (mil ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 427.91 1.97E-10 1074.67 4.98E-10 892.2432 4.11E-10 2240.815 1.04E-09 Basement 2.83E+06 1324.41 6.10E-10 3298.66 1.53E-09 2460.261 1.13E-09 6127.683 2.84E-09 Fuel Pool 2.83E+06 1048.93 4.83E-10 2660.80 1.23E-09 1948.522 8.97E-10 4942.776 2.29E-09 EVESR First Floor 2.83E+06 1292.39 5.95E-10 3428.86 1.59E-09 2400.78 1.11E-09 6369.546 2.95E-09 Basement 2.83E+06 1066.39 4.91E-10 2858.58 1.33E-09 2223.55 1.02E-09 5960.479 2.76E-09 519' Level 2.83E+06 1037.91 4.78E-10 2771.47 1.29E-09 2164.166 9.96E-10 5778.844 2.68E-09 GETR First Floor 2.83E+06 86.66 3.99E-11 219.20 1.02E-10 160.982 7.41E-11 407.192 1.89E-10 Basement 2.83E+06 93.06 4.28E-11 237.77 1.10E-10 172.8708 7.96E-11 441.6882 2.05E-10 Third Floor 2.83E+06 175.52 8.08E-11 445.04 2.06E-10 326.0508 1.50E-10 826.7187 3.83E-10 Tennelec System "A" Efficiency
 
& Conversion Factors Reactor VBWR VBWR VBWR EVESR EVESR EVESR GETR GETR GETR Alpha Efficiency 34.58% 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 34.32% 2.22E+06 7.68E+05 7.62E+05 Date Sam!;!led 12/12/2014 12/12/2014
ATTACHMENT 1 SURVEYOR (print and sign)                 IREVIEWER                      NO.
e       HITACHI VALLECITOS NUCLEAR CENTER LOCATION Name and signatures on Original at GEH Vallecitos DATE:
C-027 12/12/14 NUCLEAR SAFETY SURVEY RECORD                                       200 Area GETR Containment (page 2 of2)                         TIME:
1400 liD Routine REASON 0 Special               Annual Survey ITEMS OR LOCATION                             DOSE RATE                       DIRECT READING                   SMEAR READINGS Item                                               f3       y       n     TOTAL Distance f3y     f3y     a       a     f3y       f3r     a     a No.                                             mRad/h   mRih   mRemlh mRem/h         CPM     dPM     CPM     dPM   CPM         dPM     CPM   dPM   AREA 1 3rd Floor- Zone Area Floor Drain             60         4               64     c 2 Elevator                                             <0.5             <0.5     F                                   <100       <500     <20   <200 lOOcm 3 Basement- Clean Area*                                 <l-3             <1-3     F                                   <100       <500     <20   <200 lOOcm 4   -Filter Bank                                         I               I     F 5   -Zone Area*                                         <1-5             <1-5     F                                   200       1000     <20   <200 100 em 6   - Control Rod Storage                             1.0-50           1.0-50   c 7   - Control Rod Repair Hood                           <1-3             <1-3   F-C 8   - Autoclave I Rod Work Area                         <1               <1     c 9 Mezzanine between 2nd & 3rd Floors                   <0.5             <0.5     F                                   <100       <500     <20   <200 100 em 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                                           285                                 1339                                 897 Area Posted: (circle applicable) RA HRA   CA RMA     AIRBORNE                     PROBE   a AC- 3A (U)         10%   X PROBE     (3y PANCAKE           20%   X COMMENTS
* Whatman Smears                                                       EFF. a 43-4 (U)           10%       EFF.
(4 p                                   (4 p GEO.)                                 GEO.)
NEO 289 (REV. 07/10)


12/12/2014 12/12/2014 12/12/2014 12/12/2014 12/12/2014 12/12/2014 12/12/2014 Time On Time Off 10:55 11:20 10:25 10:50 9:55 10:20 11:45 12:10 12:40 13:05 12:10 12:35 15:30 15:55 16:00 16:25 17:00 17:25 Radon Decay Factors Sampline:
ATTACHMENT 2:              Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial                              At Sameling Time Sample            Alpha                  Beta              Alpha                Beta Reactor    Location      Volume (mil    ncpm      uCi/ml      ncpm      uCi/ml  ncpm      uCi/ml    ncpm      uCi/ml VBWR    First Floor        2.83E+06        427.91 1.97E-10      1074.67 4.98E-10 892.2432 4.11E-10 2240.815        1.04E-09 Basement            2.83E+06      1324.41 6.10E-10      3298.66 1.53E-09 2460.261 1.13E-09 6127.683        2.84E-09 Fuel Pool          2.83E+06      1048.93 4.83E-10      2660.80 1.23E-09 1948.522 8.97E-10 4942.776        2.29E-09 EVESR    First Floor        2.83E+06      1292.39 5.95E-10      3428.86 1.59E-09 2400.78 1.11E-09 6369.546          2.95E-09 Basement            2.83E+06      1066.39 4.91E-10       2858.58 1.33E-09 2223.55 1.02E-09 5960.479          2.76E-09 519' Level          2.83E+06      1037.91 4.78E-10      2771.47 1.29E-09 2164.166 9.96E-10 5778.844        2.68E-09 GETR    First Floor        2.83E+06        86.66 3.99E-11       219.20 1.02E-10 160.982 7.41E-11 407.192          1.89E-10 Basement            2.83E+06        93.06 4.28E-11        237.77 1.10E-10 172.8708 7.96E-11 441.6882        2.05E-10 Third Floor        2.83E+06        175.52 8.08E-11       445.04 2.06E-10 326.0508 1.50E-10 826.7187        3.83E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency        34.58%
Count Minutes Time Time Decay Decay Minutes Time sameled Factor Counted Time Factor Counted Factor Radon Decay Factor 25 1.316463 11:35 15 1.414216 10 1.11997 2.08511875 25 1.316463 11:00 10 1.259922 10 1.11997 1.85762782 25 1.316463 10:30 10 1.259922 10 1.11997 1.85762782 25 1.316463 12:20 10 1.259922 10 1.11997 1.85762782 25 1.316463 13:20 15 1.414216 10 1.11997 2.08511875 25 1.316463 12:50 15 1.414216 10 1.11997 2.08511875 25 1.316463 16:05 10 1.259922 10 1.11997 1.85762782 25 1.316463 16:35 10 1.259922 10 1.11997 1.85762782 25 1.316463 17:35 10 1.259922 10 1.11997 1.85762782}}
Beta Efficiency        34.32%
dpm/uCi      2.22E+06 Alpha cpm/uCi        7.68E+05 Beta cpm/uCi        7.62E+05 Radon Decay Factors Sampline:                                           Count Minutes       Time   Time     Decay     Decay     Minutes   Time Reactor    Location      Date Sam!;!led Time On  Time Off sameled         Factor Counted     Time     Factor   Counted   Factor Radon Decay Factor VBWR        First Floor    12/12/2014      10:55      11:20        25     1.316463   11:35       15   1.414216       10   1.11997   2.08511875 VBWR        Basement      12/12/2014      10:25     10:50        25    1.316463   11:00       10   1.259922       10   1.11997   1.85762782 VBWR        Fuel Pool      12/12/2014      9:55      10:20        25     1.316463   10:30       10   1.259922       10   1.11997   1.85762782 EVESR      First Floor    12/12/2014      11:45      12:10        25     1.316463   12:20       10   1.259922       10   1.11997   1.85762782 EVESR      Basement      12/12/2014      12:40      13:05        25     1.316463   13:20       15   1.414216       10   1.11997   2.08511875 EVESR      519' Level    12/12/2014      12:10      12:35        25     1.316463   12:50       15     1.414216       10   1.11997   2.08511875 GETR      First Floor    12/12/2014      15:30      15:55        25     1.316463   16:05       10     1.259922       10   1.11997   1.85762782 GETR      Basement      12/12/2014      16:00      16:25         25    1.316463   16:35       10     1.259922       10   1.11997   1.85762782 GETR      Third Floor    12/12/2014      17:00      17:25        25     1.316463   17:35       10     1.259922       10   1.11997   1.85762782}}

Latest revision as of 14:31, 31 October 2019

Boiling Water (Deactivated), Annual Report No. 50, Esada-Vallecitos Experimental Superheat Reactor (Deactivated), Annual Report No. 47 and General Electric Test Reactor(Deactivated), Annual Report No. 56 for the Year 2014
ML15092A272
Person / Time
Site: Vallecitos Nuclear Center, Vallecitos
Issue date: 03/31/2015
From:
GE-Hitachi Nuclear Energy Americas
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
Shared Package
ML15092A269 List:
References
EVESR Annual Report No. 47, GETR Annual Report No. 56, VBWR Annual Report No. 50
Download: ML15092A272 (16)


Text

HITACHI Vallecitos Nuclear Center Sunol, California VALLECITOS BOILING WATER REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 50 FOR THE VEAR 2014 LICENSE DPR-1 DOCKET 50-18 MARCH 2015

HITACHI Vallecitos Nuclear Center Sunol, California Vallecitos Boiling Water Reactor (Deactivated)

Annual Report No. 50 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. 2014 to December 31, 2014 is presented, as required by paragraph S.d.2 of the license.

1.0 SUMMARV 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 FACILITV 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 law.

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. No other significant activities

occurred at VBWR.

5.0 ORGANIZATION The organizational structure remained unchanged during 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS remains E. F. Saito.

In early 2015, prior to issuance of this report, the Manager, Regulatory Compliance and EHS changed toT. 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 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 T. A. Caine Manager Vallecitos Nuclear Center

ATTACHMENT 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signatures on Original at GEH Vallecitos D-092 HITACHI LOCATION DATE:

VALLECITOS NUCLEAR CENTER 12/12/14 TIME:

NUCLEAR SAFETY SURVEY RECORD VBWR Containment 1000 lXI Routine rEASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item p y !l TOTAL Distance fly flY a a llr f.ly a Q No. mRad/h mRJh mRam/h mR.emlh CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Main Floor - General Area <0.5 <0.5 F <100 <500 <20 <200 lOOcm 2 - Area Over Reactor Vessel <0.5 <0.5 F <100 <500 <20 <200 lOOcm 3

4 Basement - General Area <0.5 -1 <0.5. 1 F <100 <500 L<20 <200 100 em 5 -Sump 5 4 9 c 200 1000 <20 <200 lOOcm 6

7 Reactor Vessel Head Area <1 <1 F <100 <500 <20 <200 lOOcm 8

9 Top of Fuel Pool <0.5 <0.5 F <100 <500 <20 <200 100cm 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 lOOcm 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 1339 897 Area Posted: (circle appHcable) RA HRA CA RMA AIRBORNE PROSE a AC -3A {U) 10% X PROBE )ly PANCAKE 20% X OMUENTS EFF. a 43-4 (U) 10% EFF.

(4 p (4 p GEO.) GEO.)

NEO 289 (REV. 0711 0}

ATTACHMENT 2: Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial At Samgling Time Sample Alpha Beta Alpha Beta Reactor Location Volume(ml) ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 427.91 1.97E-10 1074.67 4.98E-10 892.2432 4.11£-10 2240.815 1.04E-09 Basement 2.83£+06 1324.41 6.10E-10 3298.66 1.53E-09 2460.261 1.13E-09 6127.683 2.84E-09 Fuel Pool 2.83£+06 1048.93 4.83£-10 2660.80 1.23E-09 1948.522 8.97E-10 4942.776 2.29E-Q9 EVESR First Floor 2.83E+06 1292.39 5.95E-10 3428.86 1.59E-09 2400.78 l.llE-09 6369.546 2.95E-09 Basement 2.83E+06 1066.39 4.91E-10 2858.58 1.33£-09 2223.55 1.02E-09 5960.479 2.76E-09 519'level 2.83E+06 1037.91 4.78E-10 2771.47 1.29E-09 2164.166 9.96E-10 5778.844 2.68E-09 GETR first Floor 2.83E+06 86.66 3.99E-11 219.20 1.02E-10 160.982 7.41E-11 407.192 1.89E-10 Basement 2.83E+06 93.06 4.28E-11 237.77 l.lOE-10 172.8708 7.96E-11 441.6882 2.05E-10 Third Floor 2.83E+06 175.52 8.08E-11 445.04 2.06E-10 326.0508 1.SOE-10 826.7187 3.83E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Radon Decay Factors Samolina ~

Minutes I.!.m!L Time Decay Decav Minutes Time Reactor Location Date Sameled Time On Time Off sameled Factor Counted Time Factor Counted Factor Radon Desay Factor VBWR First Floor 12/12/2014 10:55 11:20 25 1.316463 11:35 15 1.414216 10 1.11997 2.08511875 VBWR Basement 12/12/2014 10:25 10:50 25 1.316463 11:00 10 1.259922 10 1.11997 1.85762782 VBWR Fuel Pool 12/12/2014 9:55 10:20 25 1.316463 10:30 10 1.259922 10 1.11997 1.85762782 EVESR First Floor 12/12/2014 11:45 12:10 25 1.316463 12:20 10 1.259922 10 1.11997 1.85762782 EVESR Basement 12/12/2014 12:40 13:05 25 1.316463 13:20 15 1.414216 10 1.11997 2.08511875 EVESR 519' level 12/12/2014 12:10 12:35 25 1.316463 12:50 15 1.414216 10 1.11997 2.08511875 GETR First Floor 12/12/2014 15:30 15:55 25 1.316463 16:05 10 1.259922 10 1.11997 1.85762782 GETR Basement 12/12/2014 16:00 16:25 25 1.316463 16:35 10 1.259922 10 1.11997 1.85762782 GETR Third Floor 12/12/2014 17:00 17:25 25 1.316463 17:35 10 1.259922 10 1.11997 1.85762782

HITACHI Vallecitos Nuclear Center Sunol. California ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 47 FOR THE VEAR 2014 LICENSE DR-10 DOCKET 50-183 MARCH 2015

ESADA-Vallecitos EMperimental Superheat Reactor (Deactivated)

ANNUAL REPORT NO. 47 GE Hitachi Nuclear Energy (GEH) has maintained the ESADA Vallecitos Experimental Superheat Reactor (EVESRl 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, 2014 to December 31. 2014 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 549level. 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 ore 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 of2

5.0 ORGANIZATION The organizational structure remained unchanged during 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R Schrag. The Manager, Regulatory Compliance and EHS remains E. F. Saito.

In early 2015, prior to issuance of this report, the Manager. Regulatory Compliance and EHS changed to 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 T. A. Caine Manager Vallecitos Nuclear Center Page

ATIACHMENTl SURVEYOR (print and sign) !REVIEWER NO.

Name and signatures on Original at GEH Vallecitos D-093 HITACHI LOCATION DATE:

VALLECITOS NUCLEAR CENTER 12/12/14 NUCLEAR SAFETY SURVEY RECORD EVESR Containment TIME:

1200 IRI Routine REASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item p y n TOTAL Distance Jly llr (1 (I ll1 ~y a.

No. mRadlh mFUh mRemlh mRemlh 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 IOOcm 2

3 487' Level {Basement) <1 <i F 100 500 <20 <200 lOOcm 4 503'Level <0.5 <0.5 F 5 519' level <0.5 <0.5 c 150 750 <20 < lOOcm 6 534' Level -General Area <1 <I c 150 750 <20 <200 lOOcm 7 - Floor Drain <0.5 I <0.5 F 8 - Emergency Cooling Valves 4 4 c 9 549' level <0.5 <0.5 F <100 <500 <20 <200 lOOcm 10 11 Equipment Air Lock <0.5 <0.5 F <!00 <500 <20 <200 lOOcm 12 Personnel Air Lock <0.5 <0.5 F <100 <500 0 <200 lOOcm 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 285 1339 897 Area Posted: {circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC- 3A (U) 10% X PROBE ll'f PANCAKE 20% X COMMENTS EFF. a 43

  • 4 (U) 10% EFF.

(4P {4P GEO./ GEO.)

NEO 289 (REV. 07110)

ATTACHMENT 2: Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial At Same ling Time Sample Alpha Beta Alpha Beta Reactor location Volume (ml) ncpm uO/ml ncpm uCi/ml ncpm uCi/ml !l9ml uCi/ml VBWR First Floor 2.83E+06 427.91 1.97E-10 1074.67 4.98£-10 892.2432 4.11E-10 2240.815 1.04E-09 Basement 2.83E+06 1324.41 6.10£-10 3298.66 1.53E-09 2460.261 1.13£-09 6127.683 2.84E-09 Fuel Pool 2.83E+06 1048.93 4.83£-10 2660.80 1.23E-09 1948.522 8.97£-10 4942.776 2.29E-09 EVESR First Floor 2.83E+06 1292.39 5.95£-10 3428.86 1.59E-09 2400.78 l.llE-09 6369.546 2.95E-09 Basement 2.83E+06 1066..39 4.91E-10 2858.58 1.33E-09 2223.55 1.02E-09 5960.479 2.76.£-09 519' Level 2.83E+06 1037.91 4.78E*10 2771.47 1.29£-09 2164.166 9.96E-10 5778.844 2.68E-09 GETR First Floor 2.83E+06 86.66 3.99E*l1 219.20 1.02E-10 160.982 7.41E-ll 407.192 1.89E-10 Basement 2.83E+06 93.06 4.28£-11 237.77 1.10E-10 172.8708 7.96E-11 441.6882 2.05E-10 Third Floor 2.83E+06 175.52 8.08E-11 445.04 2.06E-10 326.0508 1.50E*10 826.7187 3.83E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22£+06 Alpha cpm/uCi 7.68£+05 Betacpm/uO 7.61E+05 Radon Decay Factors Samolin2 ~

Minut~s I!.m!l Time Decay Decay Minutes Time Reactor location Date Samoled Time on Time off sameled Factor Counted Time Factor Counted Factor Radon De~

VBWR First Floor 12/12/2014 10:55 11:20 25 1.316463 11:35 15 1.414216 10 1.11997 2.08511875 VBWR Basement 12/12/2014 10:25 10:50 25 1.316463 11:00 10 1.259922 10 1.11997 1.85762782 VBWR Fuel Pool 12/12/2014 9:55 10:20 25 1.316463 10:30 10 1.259922 10 1.11997 1.85762782 EVESR First Floor 12/12/2014 11:45 12:10 25 1.316463 12:20 10 1.259922 10 1.11997 1.85762782 EVESR Basement 12/12/2014 12:40 13:05 25 1.316463 13:20 15 1.414216 10 1.11997 2.08511875 EVESR 519'Level 12/12/2014 12:10 12:35 25 1.316463 12:50 15 1.414216 10 1.11997 2.08511875 GETR First Floor 12/12/2014 15:30 15:55 25 1.316463 16:05 10 1.259922 10 1.11997 1.85762782 GETR Basement 12/12/2014 16:00 16:25 25 1.316463 16:35 10 1.259922 10 1.11997 1.85762782 GETR Third Floor 12/12/2014 17:00 17:25 25 1.316463 17:35 10 1.259922 10 1.11997 1.85762782

HITACHI Vallecitos Nuclear Center Sunol, California GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 56 FOR THE VEAR 2014 LICENSE TR-1 DOCKET 50-70 MARCH 2015

GETR Annual Report No. 56 General Electric Test Reactor (Deactivated)

ANNUAL REPORT NO. 56 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. ln this annual report, a summary of the status of the facility for the period of January 1, 2014 to December 31. 2014 is presented.

1.0

SUMMARY

The facility remains in essentially the same condition described in Annual Report No. 55. 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. 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. There were no changes authorized by the Facility Manager pursuant to 10CFR50.59!al in 2014.

3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low. Results of the surveys ore presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.

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 Page 1 2

stack air flow has been documented. Stack records are available on site far review.

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 2014. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager.

Regulatory Compliance and EHS remains E. F. Saito.

In early 2015, prior to issuance of this report. the Manager, Regulatory Compliance and EHS changed toT. 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 T.A. Caine Manager Vallecitos Nuclear Center

ATTACHMENT 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signatures on Original at GEH Vallecitos C-027 HITACHI LOCATION DATE:

VALLECITOS NUCLEAR CENTER 12112114 TIME:

NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 1 of2) 1400 IRI Routine REASON D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item 13 y n TOTAL Distance jjy ~y a* ()( 13Y py a a No. mRad/h mRih mRemlh mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 em 2 Eguipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 em 3 Personnel Air Lock SOP <100 <500 <20 <200 100 em 4 1st Floor - Clean Area * <0.5 <0.5 F <100 <500 <20 <200 100 em 5 -Zone Area* <1-3 <1-3 F 1600 8000 <20 <200 100 em 6 2nd Floor- General Dose Rate <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 <200 100 em 10 -Filter Bank <1 <1 c 11 3rd Floor- Zone Area North I Floor* <1-4 <1-4 F 800 4000 <20 <200 100em 12 -Zone Area South <0.5 <0.5 F <100 <500 <20 <200 100 em 13 - Bridge I Canal 1.5 1.5 F 300 1500 <20 <200 100em 14 -Missile Shield Point A* <1 <1 F <100 <500 <20 <200 100 em 15 -Platform <0.5 <0.5 F 100 500 <20 <200 lOOem 16 - Clean Area * <0.5 <0.5 F <100 <500 <20 <200 100 em INSTRUMENT USED PRM-7 CP-5 RO -20 PNR-4 TBM- E- 120 RM- RM- PAC -1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE o. AC- 3A (U) 10% X PROBE ~y PANCAKE 20% X COMMENTS

  • Whatman Smears EFF. a 43-4 (U) 10% EFF.

(4 p (4 p GEO.) GEO.)

NEO 289 (REV. 07/10)

ATTACHMENT 1 SURVEYOR (print and sign) IREVIEWER NO.

e HITACHI VALLECITOS NUCLEAR CENTER LOCATION Name and signatures on Original at GEH Vallecitos DATE:

C-027 12/12/14 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of2) TIME:

1400 liD Routine REASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item f3 y n TOTAL Distance f3y f3y a a f3y f3r a a No. mRad/h mRih mRemlh mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 3rd Floor- Zone Area Floor Drain 60 4 64 c 2 Elevator <0.5 <0.5 F <100 <500 <20 <200 lOOcm 3 Basement- Clean Area* <l-3 <1-3 F <100 <500 <20 <200 lOOcm 4 -Filter Bank I I F 5 -Zone Area* <1-5 <1-5 F 200 1000 <20 <200 100 em 6 - Control Rod Storage 1.0-50 1.0-50 c 7 - Control Rod Repair Hood <1-3 <1-3 F-C 8 - Autoclave I Rod Work Area <1 <1 c 9 Mezzanine between 2nd & 3rd Floors <0.5 <0.5 F <100 <500 <20 <200 100 em 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 285 1339 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC- 3A (U) 10% X PROBE (3y PANCAKE 20% X COMMENTS

  • Whatman Smears EFF. a 43-4 (U) 10% EFF.

(4 p (4 p GEO.) GEO.)

NEO 289 (REV. 07/10)

ATTACHMENT 2: Air Sample Radon Calculations for Vallecitos Reactor Annual Inspection 2014 Initial At Sameling Time Sample Alpha Beta Alpha Beta Reactor Location Volume (mil ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 427.91 1.97E-10 1074.67 4.98E-10 892.2432 4.11E-10 2240.815 1.04E-09 Basement 2.83E+06 1324.41 6.10E-10 3298.66 1.53E-09 2460.261 1.13E-09 6127.683 2.84E-09 Fuel Pool 2.83E+06 1048.93 4.83E-10 2660.80 1.23E-09 1948.522 8.97E-10 4942.776 2.29E-09 EVESR First Floor 2.83E+06 1292.39 5.95E-10 3428.86 1.59E-09 2400.78 1.11E-09 6369.546 2.95E-09 Basement 2.83E+06 1066.39 4.91E-10 2858.58 1.33E-09 2223.55 1.02E-09 5960.479 2.76E-09 519' Level 2.83E+06 1037.91 4.78E-10 2771.47 1.29E-09 2164.166 9.96E-10 5778.844 2.68E-09 GETR First Floor 2.83E+06 86.66 3.99E-11 219.20 1.02E-10 160.982 7.41E-11 407.192 1.89E-10 Basement 2.83E+06 93.06 4.28E-11 237.77 1.10E-10 172.8708 7.96E-11 441.6882 2.05E-10 Third Floor 2.83E+06 175.52 8.08E-11 445.04 2.06E-10 326.0508 1.50E-10 826.7187 3.83E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Radon Decay Factors Sampline: Count Minutes Time Time Decay Decay Minutes Time Reactor Location Date Sam!;!led Time On Time Off sameled Factor Counted Time Factor Counted Factor Radon Decay Factor VBWR First Floor 12/12/2014 10:55 11:20 25 1.316463 11:35 15 1.414216 10 1.11997 2.08511875 VBWR Basement 12/12/2014 10:25 10:50 25 1.316463 11:00 10 1.259922 10 1.11997 1.85762782 VBWR Fuel Pool 12/12/2014 9:55 10:20 25 1.316463 10:30 10 1.259922 10 1.11997 1.85762782 EVESR First Floor 12/12/2014 11:45 12:10 25 1.316463 12:20 10 1.259922 10 1.11997 1.85762782 EVESR Basement 12/12/2014 12:40 13:05 25 1.316463 13:20 15 1.414216 10 1.11997 2.08511875 EVESR 519' Level 12/12/2014 12:10 12:35 25 1.316463 12:50 15 1.414216 10 1.11997 2.08511875 GETR First Floor 12/12/2014 15:30 15:55 25 1.316463 16:05 10 1.259922 10 1.11997 1.85762782 GETR Basement 12/12/2014 16:00 16:25 25 1.316463 16:35 10 1.259922 10 1.11997 1.85762782 GETR Third Floor 12/12/2014 17:00 17:25 25 1.316463 17:35 10 1.259922 10 1.11997 1.85762782