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#REDIRECT [[M200167, Amended GEH Annual Shutdown Reactor Reports for the Year 2019]]
{{Adams
| number = ML20352A287
| issue date = 12/16/2020
| title = Amended GEH Annual Shutdown Reactor Reports for the Year 2019
| author name = Feyrer M
| author affiliation = GE Hitachi Nuclear Energy
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NMSS
| docket = 05000018, 05000183
| license number =
| contact person =
| case reference number = M200167
| document type = Letter, Report, Technical
| page count = 44
}}
 
=Text=
{{#Wiki_filter:*            HITACHI                                                    GE Hitachi Nuclear Energy Matt J. Feyrer Site Manager, Vallecitos Nuclear Center 6705 Vallecitos Rd M200167                                                                 Sunol, CA 94586 USA December 16, 2020                                                        T 925 918 6018 Matt.feyrer@ge.cm U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001
 
==Subject:==
Amended GEH Annual Shutdown Reactor Reports for the Year 2019
 
==Reference:==
: 1) License DPR-1, Docket 50-18 (VBWR) , License DR-10, Docket 50-183 (EVESR), License TR-1, Docket 50-70 (GETR)
: 2) Letter M. Feyrer (GEH) to NRC Document Desk, GEH Annual Shutdown Reactor Reports for the Year 2019, 3/25/20 Enclosed is an amendment to the 2020 Annual Reports (for year 2019) for the deactivated Reactors (Vallecitos Boiling Water Reactor (VBWR), ESADA-Vallecitos Experimental Superheat Reactor (EVESR), and the General Electric Test Reactor (GETR), located at the GEH Vallecitos Nuclear Center near Sunol , California. Enclosures to this amendment are comprised of the annual reports as submitted in reference 2 but include revised radiologica l suNeys that have undergone minor editing to enhance clarity. Errata/Corrections to those suNeys are annotated in red .
If there are any questions or additional information required , please contact me at the number above.
Matt Feyrer, Site Manager Vallecitos Nuclear Center
 
==Enclosures:==
VBWR Annual Report No. 55, EVESR Annual Report No. 52, and GETR Annual Report No. 61 cc:  NRC Region IV Administrator J. Parrott, NRC NMSS MJF 20-009
 
Enclosures VBWR Annual Report No. 55 EVESR Annual Report No. 52 GETR Annual Report No. 61
* HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California VALLECITOS BOILING WATER REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 55 FOR THE YEAR 2019 LICENSE DPR-1 DOCKET 50-18 MARCH 2020
 
VBWR Annual Report No. 55 Vallecitos Boiling Water Reactor (Deactivated)
Annual Report No. 55 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWR) in a deactivated status under the authority of Amendment No. 21 to License DPR-1, Docket 50-18, issued Oct 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented, as required by paragraph S.d.2 of the license.
1.0
 
==SUMMARY==
 
All reactor systems have been removed from the containment except for the reactor vessel.
The water level within the reactor vessel was monitored and has remained essentially constant throughout the report period.
Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review.
2.0 STATUS OF FACILITY In accordance with written procedures, the Facility Manager controls access to the containment building and general systems. The facility continues to be in deactivated status in safe storage condition.
3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low.
Results of the surveys are presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.
An assessment for radionuclide distribution was performed of the shutdown reactors. An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.
Page 1 of 3
 
VBWR Annual Report No. 55 3.1 GROUND WATER MONITORING WELL Groundwater well MW-9 was installed southwest of the EVESR and VBWR shutdown reactors.
Monitoring Well 9 has two sampling points documented as MW-9S and MW-9D. These wells will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of the shutdown reactors in this area. The installation of these wells is part of the response letter to the NRC, "NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules", GEH Response Summary Dated May 31, 2019. Analytical results of groundwater samples collected from the wells during the reporting periods. These wells were sampled quarterly after installation in 2019.
Well W-9S (4S-1 E2P1)
Month      Gross Alpha Gross Beta      Tritium (pCi!L)      (pCi!L)    (pCi!L)
July 2019            2.81          1.62          0 October 2019          2.31          2.82        176 Annual Average        2.56          2.22          88 Well W-9D (4S-1 E2P2)
Month      Gross Alpha Gross Beta      Tritium (pCi!L)      (pCi!L)    (pCi!L)
July 2019            5.04          2.29        395 October 2019          4.10          0.75        270 Annual Average        4.57          1.52        333 4.0 ACTIVITIES Routine inspections were conducted during this report period. This included new monthly routines completed from February to December. Additional activities in VBWR included installation of a new automatic sump pump system in the VBWR Basement, and two monitoring wells downgradient of VBWR.
5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The VBWR Facility Manager remains K. P. Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.
Page 2 of 3
 
VBWR Annual ~eport No. 55
 
==6.0 CONCLUSION==
 
GE Hitachi Nucl ar Energy concludes that the deactivated VBWR~s being maintained in a safe shutdown cond1 ion. The inspections, access control, and administratively controlled activities ensure maximu protection for the public health and safety. The procedures will be continued to maintain this high level of protection.
GE Hitachi Nuclear Energy Vallecitos Operations
                                              ~
M.J.U.
Manager Vallecitos Nuclear Center Page 3 of 3
 
SURVEYOR (print and sign)                IREVIEWER                    NO.
e        HITACHI VALLECITOS NUCLEAR CENTER Name and signatures on Original at GEH Vallecitos LOCATION                                                              DATE:
D-055 06/18/19 TIME:
NUCLEAR SAFETY SURVEY RECORD                                            VBWR Containment                                                        0900 IRl Routine REASON D Special                Annual Survey (Revision 1) Dated 12/15/2020. Edits to Revision 1 shown in red ITEMS OR LOCATION                                  DOSE RATE                      DIRECT READING                  SMEAR READINGS Item                                                  ~        y      n    TOTAL Distance  ~y      ~y      a.      a.    ~y        ~y      a. a.
No.                                                mRad/h    mR/h    mRem/h mRem/h          CPM    dPM    CPM    dPM    CPM      dPM    CPM  dPM      AREA 1 Main Floor - General Area                                <l-5            <l-5    F 2  - Area Over Reactor Vessel                              <l              <l      F 3
4 Basement - General Area                                    <l              <l      F 5  -Sump                                                    4              4      c 6  -Sump@ l'                                                <l              <l      l' 7 Reactor Vessel Head Area                                  <l              <l      F 8
9 Top of Fuel Pool                                          <l              <l      F 10 11 Personnel Air Lock                                        <l              <l      F 12 13 Equipment Air Lock                                        <l              <l      F 14 15 Drum on First floor (Sludge)                              38              38      c 16 Drum on First floor (Sludge) @ l'                          8              8      l' INSTRUMENT USED              Tennelec  PRM-7    CP-5      RO -20      PNR-4      TBM-        E -120    RM -14    RM- 15      PAC -1SA  LUDLUM-12 SERIAL NUMBER                2972-1                        6128 Area Posted: (circle applicable)  ( RA) HRA (cAJ (RM~  AIRBORNE                      PROBE  a AC- 3A (U)        10%      PROBE    ~y  PANCAKE          20%
COMMENTS Smears completed on Tennelec see attachment                              EFF. a 43-4 (U)          10%        EFF.
Areas smeared are on maps with attachment                                (4 p                                  (4 p GEO.)                                GEO.)
NEO 289 (REV. 07/10)
 
VBWR MAIN FLOOR
                                            <1 REACTOR PIT
  <1
                                                              <1
                                    <1
                                                      <1
<1 MACHINERY HATCH g  32 CONTACT 9@30CM
                                                                <1
                                    ~
( STEAM~
                        <1
                                            )
GENERATOR              <1
                              ~ HATCH t/)
                                    ~
EQUIPMENT HAT C K
                                          <1                        #  =DOSE RATE
                                                                    @  =SMEAR LOCATION DOSE RATES IN MRIHR
 
VBWR BASEMENT AREA REACTOR HEAD E_ CONTACT
.a_@ 30CM
                                  # =DOSE RATE
                                    =SMEAR LOCATION DOSE RATES IN MRIHR
 
Attachment to Survey D-055: VBWR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument:          Tennelec XLB System A      Analyzed By:
Serial No.:          2972-2                    Signature:
Calibration Date:    1 Mar 2019                Reviewed:
Beta Efficiency:      33.47%                    Beta MDA:      16.9 dpm Alpha Efficiency:    36.28%                    Alpha MDA:    10.5 dpm Sample Date:          6/18/19                    Count Date:    6/18/19 Alpha          Alpha            Beta              Beta Level          Location      (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm 2 )
2              2 (DPM/100 cm 2 )
1                0                0            108.2                323 2                0                0            47.2                141 3                0                0            44.2                132 4                0                0            79.2                237 5                0                0            43.2                129 6                0                0            49.2                147 Main Floor              7                0.9              2.5            33.2              99.2 Levell              8                0                0            37.2                111 9                0                0            24.2              72.3 10                0.9              2.5            27.2              81.3 11                0                0            89.2                266 12                0                0            51.2                153 13                0                0            28.2              84.2 1                0.9              2.5            95.2                284 2                0                0            28.2              84.2 Rx Head 3                0                0            23.2              69.3 Level 4 (Bricks)            0                0            23.2              69.3 5 (Diamond Plate)        0.9              2.5          104.2                311 1                2.9              8.0          1944.2              5810 2                0                0            579.2              1730 3                0                0            701.2              2090 4                0                0            532.2              1590 Basement 5                0                0            691.2              2060 6                2.9              8.0          738.2              2210 7 (Sump Cover)            0                0            399.2              1190 8 (By Sump)            1.9              5.2          915 .. 2            2730 Page 1 of 1
 
VBWR & EVESR SITE MAP                        7 8                      0 0            7 CONCRETE PAD 9
MOCKUP AREA 8
10 9
8
                          &#xa9; II 9
8 8
BUILDING
\QQQj          I 1 12 10 EVESR 14 12 18                      6 16 12 20 22                                              BUILDING TANKO PAD 30 32 68 60            118 90 1000 425 80 410 180
                                                        #  :DOSE RATE DOSE RATES IN MICROREM/HR
 
ATTACHMENT 2:                Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial                              1 Hour Decay                        >24 Hour Decay Sample            Alpha                  Beta              Alpha                Beta            Alpha            Beta Reactor  Location    Volume (ml)    ncpm      uCi/ml      ncpm      uCi/ml  ncpm    uCi/ml    ncpm      uCi/ml ncpm uCi/ml        ncpm      uCi/ml VBWR    First Floor    2.83E+06      333.99 1.46E-10        792.30 3.77E-10    103.39 4.53E-11    233.50 1.11E-10  0.00 O.OOE+OO      7.00 3.33E-12 Basement        2.83E+06      820.19 3.60E-10      1991.90 9.47E-10      260.29 1.14E-10  592.20 2.81E-10    0.49 2.15E-13      21.50 1.02E-11 Fuel Pool      2.83E+06      679.59 2.98E-10      1813.90 8.62E-10      71.89 3.15E-11    159.20 7.57E-11  1.09 4.78E-13      10.30 4.90E-12 EVESR    First Floor    2.83E+06    3227.29 1.42E-09 7953.80 3.78E-09            718.89 3.15E-10 1551.40 7.37E-10    0.29 1.27E-13      5.20 2.47E-12 Basement        2.83E+06    4923.19 2.16E-09 11385.50 5.41E-09          999.79 4.38E-10 2181.90 1.04E-09    2.49 1.09E-12      75.60 3.59E-11 519' Level      2.83E+06    6876.69 3.02E-09 16930.10 8.05E-09        1534.89 6.73E-10 3353.20 1.59E-09      1.09 4.78E-13      59.90 2.85E-11 GETR    First Floor    2.83E+06      190.09 8.33E-11        548.50 2.61E-10      71.99 3.16E-11    170.30 8.09E-11  1.29 5.66E-13      8.00 3.80E-12 Basement        2.83E+06        99.59 4.37E-11        245.00 1.16E-10      29.29 1.28E-11    76.60 3.64E-11  1.09 4.78E-13      15.00 7.13E-12 Third Floor    2.83E+06      124.29 5.45E-11        458.30 2.18E-10      43.29 1.90E-11    238.00 1.13E-10  0.79 3.46E-13      43.30 2.06E-11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency        36.28%
Beta Efficiency        33.47%
dpm/uCi        2.22E+06 Alpha cpm/uCi        8.05E+05 Beta cpm/uCi        7.43E+05 Sampling Information Flow                                        Initial    1 Hr            A~~rox.
Minutes      Rate    Total                Total Sam~le  Count    Count  Minutes Half-Life Reactor    Location  Date Sam~led Time On Time Off sam~led              (cfm)  Flow {fe}  ml/fe      Volume {ml}    Time      Time    Decay    {min.}
VBWR    First Floor  6/18/2019      7:47      8:07        20          5    100.0    28317        2.83E+06      8:54      9:52      58      34.3 VBWR    Basement      6/18/2019      7:47      8:07        20          5    100.0    28317        2.83E+06      8:42      9:42      60      36.2 VBWR      Fuel Pool    6/25/2019      9:43      10:03        20          5    100.0    28317        2.83E+06    10:16    12:10    114      35.2 EVESR    First Floor  6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:39    11:55      76      35.1 EVESR    Basement      6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:49    12:05      76      33.0 EVESR    519' Level    6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:28    11:44      76      35.1 GETR    First Floor  6/17/2019      14:17      14:37        20          5    100.0    28317        2.83E+06    14:45    15:49      64      45.7 GETR    Basement      6/17/2019      9:50      10:10        20          5    100.0    28317        2.83E+06    10:58    12:00      62      35.1 GETR  Third Floor    6/25/2019      8:55        9:15        20          5    100.0    28317        2.83E+06      9:36    10:36      60      39.4
* HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 52 FOR THE YEAR 2019 LICENSE DR-10 DOCKET 50-183 MARCH 2020
 
EVESR Annual Report No. 52 ESADA-Vallecitos Experimental Superheat Reactor (Deactivated)
ANNUAL REPORT NO. 52 GE Hitachi Nuclear Energy (GEH) has maintained the ESADA Vallecitos Experimental Superheat Reactor (EVESR) in a deactivated status under the authority of Amendment No.7 to License DR-10, Docket 50-183, issued December 1, 2008. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented, as required by Amendment 7, Appendix A, Technical Specifications, section C. 1.
1.0
 
==SUMMARY==
 
Component removal activities began in 2008 above the 549-foot level. Tech Spec changes issued in Amendment 7 December 1, 2008 authorize the removal of systems beside the reactor vessel and bio-shield below the 549-level. Component removal concluded (current scope) in 2010. Entry into the containment building was made for routine radiation surveys and a general examination of conditions throughout the building. In accordance with written procedures, the Facility Manager controls access to the containment building.
Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review.
2.0 STATUS OF FACILITY The facility continues to be in deactivated status. The plugs to the reactor vessel and head storage shield, the wooden cover over the fuel storage pool remain in place.
3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low. Results of the surveys are presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.
An assessment for radionuclide distribution was performed of the shutdown reactors.
An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.
Page 1 of 3
 
EVESR Annual Report No. 52 3.1 GROUND WATER MONITORING WELL Groundwater well MW-9 was installed southwest of the EVESR and VBWR shutdown reactors. Monitoring Well 9 has two sampling points documented as MW-9S and MW-9D. These wells will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of the shutdown reactors in this area. The installation of these wells is part of the response letter to the NRC, "NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules", GEH Response Summary Dated May 31, 2019. Analytical results of groundwater samples collected from the wells during the reporting periods. These wells were sampled quarterly after installation in 2019.
Well W-9S (4S-1 E2P1)
Month      Gross Alpha Gross Beta    Tritium (pCi!L)      (pCi!L)  (pCi!L)
July 2019            2.81          1.62        0 October 2019          2.31          2.82      176 Annual Average        2.56          2.22        88 Well W-9D (4S-1 E2P2)
Month      Gross Alpha Gross Beta    Tritium (pCi!L)      (pCi!L)  (pCi!L)
July 2019            5.04          2.29      395 October 2019          4.10          0.75      270 Annual Average        4.57          1.52      333 4.0 ACTIVITIES Routine inspections were conducted during this report period. During this report period, two additional monitoring wells were installed downgradient of EVESR. No major activities occurred inside the reactor during this period.
5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The EVESR Facility Manager remains K. P.
Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.
 
==6.0 CONCLUSION==
 
GE Hitachi Nuclear Energy concludes that the deactivated ESADA-Vallecitos Experimental Superheat Reactor is being maintained in a safe shutdown condition. The Page 2 of 3
 
EVESR Annual Report No. 52 inspections, access control, and administratively controlled activities ensure maximum protection for the public health and safety. The procedures will be continued to maintain thi I high level of protection.
GE Hitachi Nuclear Energy Vallecitos Operations I
Manager Vallecitos Nuclear Center Page 3 of 3
 
SURVEYOR (print and sign)                IREVIEWER                      NO.
e        HITACHI VALLECITOS NUCLEAR CENTER Name and signatures on Original at GEH Vallecitos LOCATION                                                                DATE:
D-056 06/18/19 TIME:
NUCLEAR SAFETY SURVEY RECORD                                          EVESR Containment                                                          1100 IRl Routine REASON D Special                Annual Survey (Revision 1) Dated 12/15/2020 . Edits to Revision 1 shown in red ITEMS OR LOCATION                                DOSE RATE                      DIRECT READING                  SMEAR READINGS Item                                                  ~        y      n    TOTAL  Distance  ~y      ~y      a.      a.      ~y        ~y      a. a.
No.                                                mRad/h    mR/h    mRem/h mRem/h          CPM    dPM    CPM    dPM    CPM      dPM    CPM  dPM      AREA 1 487' Level (Basement)                                    <l              <l      F 2 503' Level                                                <l              <l      F 3 519' Level                                                <l              <l      F 4 534' Level -General Area                                  1.5            1.5      F 5  - Floor Drain                                            7              7      c 6  - Floor Drain @ l'                                      1.5            1.5      l' 7  - Emergency Cooling Valves                              4.5            4.5      F 8
9 549' Level                                                <l              <l      F 10 Equipment Air Lock                                        <l              <l      F 11 Personnel Air Lock                                        <l              <l      F 12 Top of Spent Fuel Pool (Main Floor)                    <0.5            <0.5      F 13 14 15 16 INSTRUMENT USED              Tennelec  PRM-7  CP-5        RO -20      PNR-4      TBM-        E -120    RM -14      RM- 15      PAC -1SA  LUDLUM-12 SERIAL NUMBER                2972-1                        6128 Area Posted: (circle applicable)  RA  HRA (CA ~ M9 AIRBORNE                          PROBE  a AC- 3A (U)        10%        PROBE    ~y  PANCAKE          20%
COMMENTS Smears completed on Tennelec see attachment                              EFF. a 43-4 (U)          10%        EFF.
Areas smeared are on maps with attachment                                (4 p                                  (4 p GEO.)                                  GEO.)
NEO 289 (REV. 07/10)
 
EVESR 549' LEVEL
                                                <1 ESCAPE HATCH 0
0                                      <1
            /~
                          ~              <1
                                                          ~~
I        0
                                                                        \
                              <1
            ~        &sect;
                          /              ~            \      <1 J
                                                          ~~
            <1
                                                    <1
                                                                  <1
                                <1 EQUIPMENT HATCH Dose Rates in mRem/hr
 
EVESR 534' LEVEL
      <1
      .C0
              <1 0                            *c******J**
:      RX ******
                                                                        <1
<1 DRAIN
                                !lillY 7 CONTACT 3@ 30CM
            <1
  <1 VALVE                        <1 l><l  3 CONTACT 1@ 30CM l><l ~A~~~TACT
          ~0                1@ 30CM Dose Rates in mRem/hr
 
EVESR 519' LEVEL
                /ff
        <1 0                        .....  .........
                            <1
                                                      <1 8
0 0 -
    <1
                                              <1
  \I                                      /
1/
    \
1 v                            RX STAIRS STAIR
                        /                                <1 1
                    /                  1
                    ~
Dose Rates in mRem/hr
 
EVESR 503' LEVEL
            <1
                        <1 0      <1
    <1
<1
                  <1
        <1 0
                        <1
                                      <1 Dose Rates .In mRem/hr
 
EVESR 500' LEVEL IN-CORE FLUX AREA CJ
                  <1
              <1
<1 0
              <1 Dose Rates in mRem/hr
 
EVESR 487' LEVEL
                                            &sect;          <1
          <1
                                                                                  <1
                                                                    <1
                                <1 (V
<1
      *'---~~~~~~~~~____]::
                                                                                    <1 CRD ROOM
(;;'\ <1
                  '                                            <1 v -
                                                                            <1
  <1                  <1
                                                    <1
      <1
                                                                        <1
                                        <1 Dose Rates in mRem/hr
 
Attachment to Survey D-056: EVESR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument:            Tennelec XLB System A        Analyzed By:  Names on Originals on site Serial No.:            2972-2                      Signature:    Names on Originals on site Calibration Date:      1 Mar 2019                  Reviewed:      Names on Originals on site Beta Efficiency:      33.47%                      Beta MDA:      16.9 dpm Alpha Efficiency:      36.28%                      Alpha MDA:      10.5 dpm Sample Date:          6/18/19                      Count Date:    6/18/19 Alpha            Alpha            Beta                  Beta Level          Location      (NCPM/100 cm 2 ) (DPM/100 cm 2 ) (NCPM/100 cm 2 )    (DPM/100 cm 2 )
1                  0                0              17.2                  51.4 2                  0                0              17.2                  51.4 3                  0                0              12.2                  36.4 4                0.9              2.5            16.2                  48.4 5                0.9              2.5            20.2                  60.3 549' 6                  0                0              8.2                  24.5 Levell 7                  0                0              10.2                  30.5 8                  0                0              12.2                  36.4 9                  0                0              14.2                  42.4 10                  0                0              18.2                  18.2 11                1.9              5.2            37.2                  37.2 1                  0                0            120.2                  359 2                  0                0            153.2                  458 3                  0                0            482.2                  1440 4                  0                0            207.2                  619 534'              5                  1.9              5.2            110.2                  329 Level 2            6                  0                0              95.2                  284 7                  0                0            176.2                  526 8                  0                0              36.2                  108 9                0.9              2.5            108.2                  323 10 (Fenced Area)        0.9              2.5            110.2                  329 1                  0                0              71.2                  213 519'              2                  0                0            43.2                  129 Level3            3                0.9              2.5            76.2                  228 4                0.9              2.5            189.2                  565 Page 1 of 2
 
Attachment to Survey D-056: EVESR Containment Annual Survey Smear Results Alpha            Alpha          Beta              Beta Level        Location    (NCPM/100 cm 2 )  (DPM/100 cm 2 ) (NCPM/100 cm 2 ) (DPM/100 cm 2 )
5                0                0            77.2              231 6                0                0            48.2              144 1                0                0            111.2              332 2                0                0            883.2            2,640 3              2.89              8.0          124.2              371 503'            4                0                0            78.2              234 Level4 5                0                0            129.2              386 6                0                0            193.2              577 7                0                0            95.2              284 8              0.89              2.5          281.2              840 1                0                0            144.2              431 500'            2                0                0            23.2            69.3 In-Core 3                0                0            298.2              891 Flux Level 4                0                0            3650            10,900 1                0                0            106.2              317 2                0                0            326.2              975 3              1.89              5.2          130.2              389 4              1.89              5.2          140.2              419 5                0                0            47.2              141 487' 6                0                0            68.2              204 Basement 7                0                0            118.2              353 8                0                0            244.2              730 9                0                0            210.2              628 10              0.89              2.5          335.2            1000 11              0.89              2.5          470.2            1400 Page 2 of 2
 
VBWR & EVESR SITE MAP                        7 8                      0 0            7 CONCRETE PAD 9
MOCKUP AREA 8
10 9
8
                          &#xa9; II 9
8 8
BUILDING
\QQQj          I 1 12 10 EVESR 14 12 18                      6 16 12 20 22                                              BUILDING TANKO PAD 30 32 68 60            118 90 1000 425 80 410 180
                                                        #  :DOSE RATE DOSE RATES IN MICROREM/HR
 
ATTACHMENT 2:                Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial                              1 Hour Decay                        >24 Hour Decay Sample            Alpha                  Beta              Alpha                Beta            Alpha            Beta Reactor  Location    Volume (ml)    ncpm      uCi/ml      ncpm      uCi/ml  ncpm    uCi/ml    ncpm      uCi/ml ncpm uCi/ml        ncpm      uCi/ml VBWR    First Floor    2.83E+06      333.99 1.46E-10        792.30 3.77E-10    103.39 4.53E-11    233.50 1.11E-10  0.00 O.OOE+OO      7.00 3.33E-12 Basement        2.83E+06      820.19 3.60E-10      1991.90 9.47E-10      260.29 1.14E-10  592.20 2.81E-10    0.49 2.15E-13      21.50 1.02E-11 Fuel Pool      2.83E+06      679.59 2.98E-10      1813.90 8.62E-10      71.89 3.15E-11    159.20 7.57E-11  1.09 4.78E-13      10.30 4.90E-12 EVESR    First Floor    2.83E+06    3227.29 1.42E-09 7953.80 3.78E-09            718.89 3.15E-10 1551.40 7.37E-10    0.29 1.27E-13      5.20 2.47E-12 Basement        2.83E+06    4923.19 2.16E-09 11385.50 5.41E-09          999.79 4.38E-10 2181.90 1.04E-09    2.49 1.09E-12      75.60 3.59E-11 519' Level      2.83E+06    6876.69 3.02E-09 16930.10 8.05E-09        1534.89 6.73E-10 3353.20 1.59E-09      1.09 4.78E-13      59.90 2.85E-11 GETR    First Floor    2.83E+06      190.09 8.33E-11        548.50 2.61E-10      71.99 3.16E-11    170.30 8.09E-11  1.29 5.66E-13      8.00 3.80E-12 Basement        2.83E+06        99.59 4.37E-11        245.00 1.16E-10      29.29 1.28E-11    76.60 3.64E-11  1.09 4.78E-13      15.00 7.13E-12 Third Floor    2.83E+06      124.29 5.45E-11        458.30 2.18E-10      43.29 1.90E-11    238.00 1.13E-10  0.79 3.46E-13      43.30 2.06E-11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency        36.28%
Beta Efficiency        33.47%
dpm/uCi        2.22E+06 Alpha cpm/uCi        8.05E+05 Beta cpm/uCi        7.43E+05 Sampling Information Flow                                        Initial    1 Hr            A~~rox.
Minutes      Rate    Total                Total Sam~le  Count    Count  Minutes Half-Life Reactor    Location  Date Sam~led Time On Time Off sam~led              (cfm)  Flow {fe}  ml/fe      Volume {ml}    Time      Time    Decay    {min.}
VBWR    First Floor  6/18/2019      7:47      8:07        20          5    100.0    28317        2.83E+06      8:54      9:52      58      34.3 VBWR    Basement      6/18/2019      7:47      8:07        20          5    100.0    28317        2.83E+06      8:42      9:42      60      36.2 VBWR      Fuel Pool    6/25/2019      9:43      10:03        20          5    100.0    28317        2.83E+06    10:16    12:10    114      35.2 EVESR    First Floor  6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:39    11:55      76      35.1 EVESR    Basement      6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:49    12:05      76      33.0 EVESR    519' Level    6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:28    11:44      76      35.1 GETR    First Floor  6/17/2019      14:17      14:37        20          5    100.0    28317        2.83E+06    14:45    15:49      64      45.7 GETR    Basement      6/17/2019      9:50      10:10        20          5    100.0    28317        2.83E+06    10:58    12:00      62      35.1 GETR  Third Floor    6/25/2019      8:55        9:15        20          5    100.0    28317        2.83E+06      9:36    10:36      60      39.4
* HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 61 FOR THE YEAR 2020 LICENSE TR-1 DOCKET 50-70 MARCH 2020
 
GETR Annual Report No. 61 General Electric Test Reactor (Deactivated)
ANNUAL REPORT NO. 61 GE Hitachi (GEH) has maintained the General Electric Test Reactor (GETR) in a deactivated status under the authority of Amendment No. 17 to License TR-1, Docket 50-70, issued October 22, 2007, as specified in TS 6.6.1 to Amendment No. 14, issued February 5, 1986. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented.
1.0
 
==SUMMARY==
 
The facility remains in essentially the same condition described in Annual Report No. 60.
Entry into the reactor building was made for routine radiation surveys and a general examination of conditions throughout the building. The crane, elevator, and ventilation were serviced and tested in 2011 in anticipation of beginning remediation activities.
Such activities have not begun.
Radiation and contamination levels remain at acceptable levels.
2.0 STATUS OF FACILITY In accordance with written procedures, the Facility Manager controls access to the containment building and general systems. The facility continues to be in deactivated status. There were no changes authorized by the Facility Manager pursuant to 10CFR50.59(a) in 2019.
3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low. Results of the surveys are presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.
Radiological surveys were performed in June 2019, in unknown areas that had not been surveyed previously using Change Authorization 19-05. Entries into these areas was Page 1 of 4
 
GETR Annual Report No. 61 performed using SCBA and full-face respiratory protection. Radiological surveys are available for review at VNC. Some of the areas were found to have high radiation levels and high levels of contamination. Areas were posted as required by regulation based on survey resu Its.
An assessment for radionuclide distribution was performed of the shutdown reactors.
An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.
3.1    GETR Stack Although maintenance was performed on the stack in 2011, and the stack was tested, there has been no remediation effort performed for the GETR reactor. The ventilation system is operational, but not currently in use.
GETR Stack was operational from June to November 2019, during entries made into unknown areas for surveying purposes. The data listed below is from the GETR stack.
GETR Stack Month            Beta (uCi)    Alpha (uCi)
May 2019                    0.00        1.77E-02 June 2019                3.48E-03        3.67E-01 July 2019                1.39E-03        6.36E-02 August 2019              7.33E-03        5.59E-01 September 2019            6.57E-03        1.78E-01 October 2019              5.74E-03        1.14E-01 November 2019            6.91 E-03      1.73E-01 Total (Annual)            3.14E-02      1.47E+OO 3.2    Gamma Radiation The yearly dose results for the year 2019 as determined from evaluation of site perimeter environmental monitoring dosimeters showed no departure from normal stable backgrounds.
3.3    Vegetation No alpha, beta or gamma activity attributable to activities at the GETR facility was found on or in vegetation in the vicinity of the site.
Page 2 of 4
 
GETR Annual Report No. 61 3.4      Ground Water Monitoring Well Data Analytical results of groundwater samples collected from the B-2 (GETR) well during the reporting periods. The GETR well was sampled quarterly in 2019. During the fourth quarter sampling period, a sample was not collected from the B-2 well due to a blockage caused by the sampling bag. Condition Report# 33068 was entered into the Condition Report System.
GETR Well B-2 Month        Gross      Gross Beta      Tritium Alpha        (pCi!L)      (pCi!L)
(pCi!L)
January 2019        9.36          2.76        522 April2019            3.93          3.24        149 August 2019          6.50            2.47        318 November 2019    No Sample Collected CR # 33068 Groundwater well MW-8 was installed southwest of the GETR shutdown reactor. The well will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of GETR. The installation of the well is part of the response letter to the NRC, "NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules", GEH Response Summary Dated May 31, 2019. Well was sampled quarterly in 2019 after installation.
Well W-8 (4S-1 E2M01)
Month      Gross Alpha Gross Beta        Tritium (pCi!L)          (pCi!L)  (pCi!L)
July 2019              6.86            1.51      371 October 2019          1.32            2.28      798 Annual Average        4.09            1.90      585 4.0 ACTIVITIES Routine inspections were conducted during this report period. A small amount of water
(<5 gallon) was identified in the elevator sump area of GETR. The water was removed (CR# 31626), and gamma spectroscopy was performed. Results were normal. There were no preventive or corrective maintenance activities performed having safety significance during the reporting period.
5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The GETR Facility Manager remains K. P.
Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.
Page 3 of 4
 
GETR Annual Report No. 61
 
==6.0 CONCLUSION==
 
GE Hitachi Nuclear Energy concludes that the deactivated GETR is being maintained in a safe shutdown condition . The inspections, access control, and 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 3~
Manager Vallecitos Nuclear Center Page 4 of4
 
SURVEYOR (print and sign)                IREVIEWER                      NO.
e        HITACHI VALLECITOS NUCLEAR CENTER Name and signatures on Original at GEH Vallecitos LOCATION                                                                DATE:
C-020 06/17/19 TIME:
NUCLEAR SAFETY SURVEY RECORD                                            200 Area GETR Containment (page 1 of 2)                                    1100 IRl Routine REASON D Special                    Annual Survey (Revision 1) Dated 12/15/2020 . Edits to Revision 1 shown in red ITEMS OR LOCATION                                  DOSE RATE                        DIRECT READING                  SMEAR READINGS Item                                                      ~        y      n    TOTAL  Distance  ~y      ~y      a.      a.      ~y      ~y      a. a.
No.                                                    mRad/h  mR/h    mRem/h  mRem/h          CPM      dPM    CPM    dPM    CPM      dPM    CPM  dPM    AREA 1 Personnel Air Lock                                          <l              <l        F 2 Equipment Air Lock                                          <l              <l        F 3  Personnel Air Lock SOP                                      <l              <l        F 4 l st Floor - Clean Area                                      <l              <l        F 5    -Zone Area                                                <l              <l        F 6  2nd Floor - General Dose Rate                                <l              <l        F 7    - EEHS Cubicle Door                                        7              7        c 8    - Field Reading Around EEHS Cubicle                        5              5        F 9    - Filter Bank                                            <l              <l        c 10    - Filter Bank downstairs                                  5              5        F 11 3rd Floor- Zone Area North                                  1.5            1.5      F 12    - Zone Area South                                          l              l        F 13    -Bridge                                                  1.5            1.5      F 14    - Missile Shield                                          <l              <l        F 15    -Platform                                                <l              <l        F 16    -Clean Area                                              <l              <l        F INSTRUMENT USED                Tennelec  PRM-7  CP- 5      R0-20      PNR-4      TBM-        E- 120      RM -14      RM -15      PAC- lSA  LUDLUM-12 SERIAL NUMBER                  2972-1                        6128 Area Posted: (circle applicable)  RA    HRA  ~A) ~ AIRBORNE                              PROBE    a AC-3A (U)        10%        PROBE    bg PANCAKE          20%
COMMENTS Smears completed on Tennelec see attachment                                EFF    a 43- 4 (U)        10%        EFF Areas smeared are on maps with attachment                                  (4P                                    (4P GEO.)                                  GEO.)
NEO 289 (REV. 07/10)
 
SURVEYOR (print and sign)                    IREVIEWER                    NO.
e        HITACHI VALLECITOS NUCLEAR CENTER Name and signatures on Original at GEH Vallecitos LOCATION                                                                  DATE:
C-020 06/17/19 TIME:
NUCLEAR SAFETY SURVEY RECORD                                                  200 Area GETR Containment (page 2 of 2)                                    1100 X  Routine REASON 0  Special                    Annual Survey (Revision 1) Dated 12/15/2020. Edits to Revision 1 shown in red ITEMS OR LOCATION                                  DOSE RATE                          DIRECT READING                  SMEAR READINGS Item                                                        b        g        n      TOTAL Distance  bg        bg      a      a        bg      bg      a      a No.                                                    rnRad!h    rnR!h  rnRern!h rnRern!h        CPM      dPM    CPM    dPM    CPM      dPM    CPM    dPM    AREA 1 3rd Floor- Zone Area Floor Drain                                6                6        c 2 Elevator                                                        <1                <1        F 3 Basement - Clean Area                                            <1                <1        F 4    - Filter Bank                                                <1                <1        F 5    -Zone Area                                                    3                3        F 6    - Control Rod Storage                                        <1                <1        c 7    - Control Rod Repair Hood                                    <1                <1        c 8    -Autoclave                                                    2                2        c 9  Mezzanine between 2nd & 3rd Floors                              <1                <1        F 10 B-1 Basement General Area                                        5                5        F 11 B-1 Basement Pipe                                              120                120        c 12 B-1 Basement Pipe @ 1'                                          15                15        1' 13 B-2/B Basement General Area                                  <1                <1        F 14 B-3 Basement General Area                                      <1                <1        F 15 Heat Exchange                                                  25                25        c 16 Heat Exchange Room General Area                                <1                <1        F INSTRUMENT USED                  Tennelec  PRM-7  CP- 5        R0-20        PNR-4        TBM-      E- 120      RM- 14    RM- 15      PAC- 1SA  LUDLUM-12 SERIAL NUMBER                    2972-1                          6128 Area Posted:  (circle applicable)  RA    HRA  ~A)~ ~) AIRBORNE                                PROBE  a AC-3A (U)        10%        PROBE bg PANCAKE            20%
COMMENTS Smears completed on Tennelec see attachment                                    EFF    a 43- 4 (U)        10%        EFF Areas smeared are on maps with attachment                                        (4P                                    (4P GEO.)                                  GEO.)
NEO 289 (REV. 07/10)
 
GETR Basement
                                                                                  <1        CyL.IIIIO&#xa3;R Sl'oRAG&#xa3; A.R&#xa3;A
                                                                                        <1
                                                                                                                  <1
                                                    <1
:. :: ..                  f::\ CRD R~ ~ontact          <1
                                                                                                  ~
                                                        ...                            <1
              *                                                                                                ' @30cm
:. :: ..                          1
<1
:o:
                ~12o conta 15
                                @ 30c G* @                              <1 STAIRS
                                                                                                                                              <1 3                                    : :: .. :::: :
  <1                                <1                                                                                          <1
                                                                                                        <1
              . .. . :**  .. ::: * *:: :: .. *:: :: ..                  **::: :  <1 AUTOCLAVE ELEVATOR
                                                                                                            <1
                                                              <1        @
                                                                                                                        .1L = Dose Rate
                                                                                                                        @=Smear Location Dose Rates in mR/hr
 
GETR Level1
  <1 @
                    <1    @
<1
                <1    @
f;  <1 15 contact @ /
6 @ 30cm
                      <1
                              .JL = Dose Rate
                              @= Smear Location Do se Rates in mR/hr
 
GETR Level2
                                <1
            <1
                                    <1 EEHS
                                                      <1 7 contact 4@ 30cm STAIRS Rx
                                <1
                        <1
                      ~                    <1
              ~ 1~contac
        <1 ELEVATOR
                            <1
      <1
                                        .JL = Dose Rate
                                        = Smear Location Dose Rate s in mR/hr
 
GETR Level3 Mezzine
          <1
                      <1
                                      <1
                  <1 STAIRS Rx
              <1 G)    <1
                    .JL = Dose Rate Gi)= Smear Location Dose Rates in mR/hr
 
GETR Level4
                                                    <1
                <1
                          <1
                                                            <1
                                            <1 RAISED PLATFORM AREA
                                                                                  <1
    <1
                                                            <1
                          <1
                                                <1 STAIRS REACTOR HEAD REACTOR CAVITY                    &
MISSILE SHIELD
                                                                  <1
                            <1
  <1
                                                    <1                  G)
                                                                                    <1 (iV
              <1                        Drain
                                              *5 contact 1.5 @ 30c                            @
                            <1                                            <1
                                                        <1 ELEVATOR OFFICE t:~\
                                      <1
                      <1 @
                                                                            ..1L = Dose Rate
                                                                            @= Smear Location Dose Rates in mR/hr
 
Attachment to Survey C-020: GETR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument:          Tennelec XLB System A      Analyzed By:    Names on Originals on site Serial No.:          2972-2                      Signature:      Names on Originals on site Calibration Date:    1 Mar 2019                  Reviewed:        Names on Originals on site Beta Efficiency:      33.47%                      Beta MDA:        16.9 dpm Alpha Efficiency:    36.28%                      Alpha MDA:      10.5 dpm Sample Date:          6/17/19                    Count Date:      6/17/19 Alpha            Alpha                Beta        Beta Level                  Location              (NCPM/100 cm 2 ) (DPM/100 cm 2 ) (NCPM/100 cm 2 ) (DPM/100 cm 2 )
1 (Zone Floor)                        0.9              2.5                72          216 2 (Zone Floor)                        0.9              2.5                63          189 3 (Zone Floor)                        0.0              0.0                335          1,001 4 (Zone Flats)                        0.9              2.5                42          126 5 (Zone Flats)                        0.0              0.0                24            72 6 (Zone Floor - Left of SOP)          0.0              0.0                598          1,787 Main        7 (Zone Floor - Right of SOP)          0.0              0.0                340          1,016 Floor 8 (By Ladder)                          0.0              0.0              1,075        3,212 Level 1 Flats behind GE Logo                  0.0              0.0                17            51 Floor Behind GE Logo                  0.9              2.5                67          201 CA Area Floor Near Entrance            0.0              0.0                15            45 Equipment Air Lock                    0.0              0.0                  1            4 Clean Floor Near Entrance              0.9              2.5                26            78 Personnel Air Lock SOP                0.0              0.0                  1            4 Zone Area CRD Rack                    0.0              0.0                61          183 Zone Area Table                        0.9              2.5                35          105 HeatExchanger(HX)Room                  0.0              0.0                25            75 Elevator                              0.9              2.5                32            96 Clean Area                            0.0              0.0                17            51 Basement      Zone Area Rod Repair Hood              3.9              10.7              12,174        36,373 Zone Area Floor                        0.0              0.0                548          1,638 Room B-3 Flats                        0.0              0.0                151          452 Room B-3 Floor                        0.0              0.0                42          126 Room B-3 Floor @ Door                  0.9              2.5                925          2,764 Under Vessel - Flats                  1.9              5.2                75          225 Page 1 of 3
 
Attachment to Survey C-020: GETR Containment Annual Survey Smear Results Alpha          Alpha            Beta        Beta Level              Location              (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm ) (DPM/100 cm 2 )
2            2                  2 Under Vessel- Floor                    0.9            2.5            157          470 Under Vessel - Rust Floor              0.0            0.0            1,322        3,950 Basement: Under HX Room                0.9            2.5              59          177 HX Room Lead Shield                    0.9            2.5              21          63 HX Room Flats/Pipes                    0.9            2.5              54          162 Basement  Pump Room (B-1)                        0.0            0.0            117          350 Pump Room (B-1) Floor                  0.0            0.0              60          180 Pump Room (B-1) Flats                  0.0            0.0              64          192 Pump Room (B-1) Floor                  0.0            0.0              60          180 Inside, Only Entrance Hot Spot        0.0            0.0            2,917        8,716 Only Entrance Pump                    0.0            0.0            261          780 Only Entrance Drain                    0.0            0.0            2,575        7,694 Elevator                              0.9            2.5              11          33 1                                      0.0            0.0              3          10 Level 2 2                                      0.0            0.0              6          19 3                                      0.0            0.0              31          93 4 (@Stairs)                            0.9            2.5              41          123 5                                      0.9            2.5              47          141 6 (@ Back Stairs Area)                0.9            2.5              34          102 Room 1 Floor                          0.9            2.5            138          413 Room 1 Flats                          1.9            5.2            157          470 Level 2.5 General Area 1                        1.9            5.2              11          33 Mezzanine General Area 2                        1.9            5.2              18          54 General Area 3                        0.0            0.0              32          96 Top of Bathroom                        0.9            2.5              39          117 Under Platform #1 Floor                0.9            2.5              39          117 Under Platform #2 Floor                0.0            0.0            129          386 Floor (1) @ Stairs                    0.0            0.0            100          299 Floor (2) Left of Stairs              0.0            0.0              26          78 Floor (3)@ Bathroom                    0.0            0.0              50          150 Level 3 Floor (4)@ Elevator                    0.0            0.0              36          108 Top Floor Floor (5) @ Platform Stairs            0.9            2.5            135          404 Floor (6) Left of Missile Shield      0.0            0.0            354        1,058 Floor (7) Left side of Cavity          0.0            0.0            444        1,327 Floor (8) Right of Missile Shield      0.0            0.0            211          631 Floor (9) Right of Cavity              0.0            0.0            2,944        8,797 Floor (10) By Straight Ladder          0.0            0.0            1,083        3,236 Page 2 of 3
 
Attachment to Survey C-020: GETR Containment Annual Survey Smear Results Alpha            Alpha            Beta            Beta Level                Location            (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm ) (DPM/100 cm 2 )
2              2                2 Missile Shield (11)                      0.0              0.0              147            440 Upper Deck (12)                          0.9              2.5              24              72 Upper Deck (13)                          2.9              8.0              48              144 Upper Deck (14)                          0.0              0.0              32              96 Level 3    Flats (15)                              0.0              0.0              23              69 Top Floor  Flats (16)                              3.9            10.7              127            380 Bridge (17)                              0.9              2.5              234            700 Flats- Spreader Bar (18)                0.9              2.5              131            392 Alpha            Alpha            Beta            Beta Level                Location                  (NCPM)          (DPM)          (NCPM)            (DPM)
EEHS Floor- 1                          76.9            211.9          334207          998527 EEHS Floor- 2                          21.9            60.3          31243            93346 EEHS Floor- 3                            3.9            10.7          73920            220855 EEHS Flats- 1                            5.9            16.2            36608          109376 Level 2 EEHS Flats- 2                            0.9              2.5            24.2            72.3 EEHS Flats- 3                            7.9            21.7            9786            29238 EEHS Flats- 4                            0.9              2.5            2370            7081 EEHS Flats- 5                            9.9            27.3            29546            88276 Note: The smears in the Experiment Effluent Hold-up System (EEHS) room were taken with disk smears, but were not limited to 100 cm 2
* Page 3 of 3
 
GETR SITE MAP
('*\(~\\ ~"'""'j            17
            ~
19
                                      \\ ....                  35
~
BUILDING 40 60 24 14                                                        30 20 25 32 GETR 25 36 50 60
                              ~
47 oG      300 a2800
                    "<~'-""            450 I
1200 600
            ~                                    \'io BUILDING  ~ 10 o 0 0 35
                                                                      # = DOSE RATE 14 20 DOSE RATES IN MICROREM/HR 17
 
ATTACHMENT 2:                Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial                              1 Hour Decay                        >24 Hour Decay Sample            Alpha                  Beta              Alpha                Beta            Alpha            Beta Reactor  Location    Volume (ml)    ncpm      uCi/ml      ncpm      uCi/ml  ncpm    uCi/ml    ncpm      uCi/ml ncpm uCi/ml        ncpm      uCi/ml VBWR    First Floor    2.83E+06      333.99 1.46E-10        792.30 3.77E-10    103.39 4.53E-11    233.50 1.11E-10  0.00 O.OOE+OO      7.00 3.33E-12 Basement        2.83E+06      820.19 3.60E-10      1991.90 9.47E-10      260.29 1.14E-10  592.20 2.81E-10    0.49 2.15E-13      21.50 1.02E-11 Fuel Pool      2.83E+06      679.59 2.98E-10      1813.90 8.62E-10      71.89 3.15E-11    159.20 7.57E-11  1.09 4.78E-13      10.30 4.90E-12 EVESR    First Floor    2.83E+06    3227.29 1.42E-09 7953.80 3.78E-09            718.89 3.15E-10 1551.40 7.37E-10    0.29 1.27E-13      5.20 2.47E-12 Basement        2.83E+06    4923.19 2.16E-09 11385.50 5.41E-09          999.79 4.38E-10 2181.90 1.04E-09    2.49 1.09E-12      75.60 3.59E-11 519' Level      2.83E+06    6876.69 3.02E-09 16930.10 8.05E-09        1534.89 6.73E-10 3353.20 1.59E-09      1.09 4.78E-13      59.90 2.85E-11 GETR    First Floor    2.83E+06      190.09 8.33E-11        548.50 2.61E-10      71.99 3.16E-11    170.30 8.09E-11  1.29 5.66E-13      8.00 3.80E-12 Basement        2.83E+06        99.59 4.37E-11        245.00 1.16E-10      29.29 1.28E-11    76.60 3.64E-11  1.09 4.78E-13      15.00 7.13E-12 Third Floor    2.83E+06      124.29 5.45E-11        458.30 2.18E-10      43.29 1.90E-11    238.00 1.13E-10  0.79 3.46E-13      43.30 2.06E-11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency        36.28%
Beta Efficiency        33.47%
dpm/uCi        2.22E+06 Alpha cpm/uCi        8.05E+05 Beta cpm/uCi        7.43E+05 Sampling Information Flow                                        Initial    1 Hr            A~~rox.
Minutes      Rate    Total                Total Sam~le  Count    Count  Minutes Half-Life Reactor    Location  Date Sam~led Time On Time Off sam~led              (cfm)  Flow {fe}  ml/fe      Volume {ml}    Time      Time    Decay    {min.}
VBWR    First Floor  6/18/2019      7:47      8:07        20          5    100.0    28317        2.83E+06      8:54      9:52      58      34.3 VBWR    Basement      6/18/2019      7:47      8:07        20          5    100.0    28317        2.83E+06      8:42      9:42      60      36.2 VBWR      Fuel Pool    6/25/2019      9:43      10:03        20          5    100.0    28317        2.83E+06    10:16    12:10    114      35.2 EVESR    First Floor  6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:39    11:55      76      35.1 EVESR    Basement      6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:49    12:05      76      33.0 EVESR    519' Level    6/18/2019      9:34      9:54        20          5    100.0    28317        2.83E+06    10:28    11:44      76      35.1 GETR    First Floor  6/17/2019      14:17      14:37        20          5    100.0    28317        2.83E+06    14:45    15:49      64      45.7 GETR    Basement      6/17/2019      9:50      10:10        20          5    100.0    28317        2.83E+06    10:58    12:00      62      35.1 GETR  Third Floor    6/25/2019      8:55        9:15        20          5    100.0    28317        2.83E+06      9:36    10:36      60      39.4}}

Latest revision as of 02:51, 3 March 2022

Amended GEH Annual Shutdown Reactor Reports for the Year 2019
ML20352A287
Person / Time
Site: Vallecitos Nuclear Center, Vallecitos
Issue date: 12/16/2020
From: Feyrer M
GE Hitachi Nuclear Energy
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
M200167
Download: ML20352A287 (44)
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Text

  • HITACHI GE Hitachi Nuclear Energy Matt J. Feyrer Site Manager, Vallecitos Nuclear Center 6705 Vallecitos Rd M200167 Sunol, CA 94586 USA December 16, 2020 T 925 918 6018 Matt.feyrer@ge.cm U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001

Subject:

Amended GEH Annual Shutdown Reactor Reports for the Year 2019

Reference:

1) License DPR-1, Docket 50-18 (VBWR) , License DR-10, Docket 50-183 (EVESR), License TR-1, Docket 50-70 (GETR)
2) Letter M. Feyrer (GEH) to NRC Document Desk, GEH Annual Shutdown Reactor Reports for the Year 2019, 3/25/20 Enclosed is an amendment to the 2020 Annual Reports (for year 2019) for the deactivated Reactors (Vallecitos Boiling Water Reactor (VBWR), ESADA-Vallecitos Experimental Superheat Reactor (EVESR), and the General Electric Test Reactor (GETR), located at the GEH Vallecitos Nuclear Center near Sunol , California. Enclosures to this amendment are comprised of the annual reports as submitted in reference 2 but include revised radiologica l suNeys that have undergone minor editing to enhance clarity. Errata/Corrections to those suNeys are annotated in red .

If there are any questions or additional information required , please contact me at the number above.

Matt Feyrer, Site Manager Vallecitos Nuclear Center

Enclosures:

VBWR Annual Report No. 55, EVESR Annual Report No. 52, and GETR Annual Report No. 61 cc: NRC Region IV Administrator J. Parrott, NRC NMSS MJF 20-009

Enclosures VBWR Annual Report No. 55 EVESR Annual Report No. 52 GETR Annual Report No. 61

  • HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California VALLECITOS BOILING WATER REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 55 FOR THE YEAR 2019 LICENSE DPR-1 DOCKET 50-18 MARCH 2020

VBWR Annual Report No. 55 Vallecitos Boiling Water Reactor (Deactivated)

Annual Report No. 55 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWR) in a deactivated status under the authority of Amendment No. 21 to License DPR-1, Docket 50-18, issued Oct 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented, as required by paragraph S.d.2 of the license.

1.0

SUMMARY

All reactor systems have been removed from the containment except for the reactor vessel.

The water level within the reactor vessel was monitored and has remained essentially constant throughout the report period.

Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review.

2.0 STATUS OF FACILITY In accordance with written procedures, the Facility Manager controls access to the containment building and general systems. The facility continues to be in deactivated status in safe storage condition.

3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the facility indicate that levels remain low.

Results of the surveys are presented in attachment 1. Air sampling results are presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.

An assessment for radionuclide distribution was performed of the shutdown reactors. An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.

Page 1 of 3

VBWR Annual Report No. 55 3.1 GROUND WATER MONITORING WELL Groundwater well MW-9 was installed southwest of the EVESR and VBWR shutdown reactors.

Monitoring Well 9 has two sampling points documented as MW-9S and MW-9D. These wells will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of the shutdown reactors in this area. The installation of these wells is part of the response letter to the NRC, "NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules", GEH Response Summary Dated May 31, 2019. Analytical results of groundwater samples collected from the wells during the reporting periods. These wells were sampled quarterly after installation in 2019.

Well W-9S (4S-1 E2P1)

Month Gross Alpha Gross Beta Tritium (pCi!L) (pCi!L) (pCi!L)

July 2019 2.81 1.62 0 October 2019 2.31 2.82 176 Annual Average 2.56 2.22 88 Well W-9D (4S-1 E2P2)

Month Gross Alpha Gross Beta Tritium (pCi!L) (pCi!L) (pCi!L)

July 2019 5.04 2.29 395 October 2019 4.10 0.75 270 Annual Average 4.57 1.52 333 4.0 ACTIVITIES Routine inspections were conducted during this report period. This included new monthly routines completed from February to December. Additional activities in VBWR included installation of a new automatic sump pump system in the VBWR Basement, and two monitoring wells downgradient of VBWR.

5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The VBWR Facility Manager remains K. P. Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.

Page 2 of 3

VBWR Annual ~eport No. 55

6.0 CONCLUSION

GE Hitachi Nucl ar Energy concludes that the deactivated VBWR~s being maintained in a safe shutdown cond1 ion. The inspections, access control, and administratively controlled activities ensure maximu protection for the public health and safety. The procedures will be continued to maintain this high level of protection.

GE Hitachi Nuclear Energy Vallecitos Operations

~

M.J.U.

Manager Vallecitos Nuclear Center Page 3 of 3

SURVEYOR (print and sign) IREVIEWER NO.

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

D-055 06/18/19 TIME:

NUCLEAR SAFETY SURVEY RECORD VBWR Containment 0900 IRl Routine REASON D Special Annual Survey (Revision 1) Dated 12/15/2020. Edits to Revision 1 shown in red ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item ~ y n TOTAL Distance ~y ~y a. a. ~y ~y a. a.

No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Main Floor - General Area <l-5 <l-5 F 2 - Area Over Reactor Vessel <l <l F 3

4 Basement - General Area <l <l F 5 -Sump 4 4 c 6 -Sump@ l' <l <l l' 7 Reactor Vessel Head Area <l <l F 8

9 Top of Fuel Pool <l <l F 10 11 Personnel Air Lock <l <l F 12 13 Equipment Air Lock <l <l F 14 15 Drum on First floor (Sludge) 38 38 c 16 Drum on First floor (Sludge) @ l' 8 8 l' INSTRUMENT USED Tennelec PRM-7 CP-5 RO -20 PNR-4 TBM- E -120 RM -14 RM- 15 PAC -1SA LUDLUM-12 SERIAL NUMBER 2972-1 6128 Area Posted: (circle applicable) ( RA) HRA (cAJ (RM~ AIRBORNE PROBE a AC- 3A (U) 10% PROBE ~y PANCAKE 20%

COMMENTS Smears completed on Tennelec see attachment EFF. a 43-4 (U) 10% EFF.

Areas smeared are on maps with attachment (4 p (4 p GEO.) GEO.)

NEO 289 (REV. 07/10)

VBWR MAIN FLOOR

<1 REACTOR PIT

<1

<1

<1

<1

<1 MACHINERY HATCH g 32 CONTACT 9@30CM

<1

~

( STEAM~

<1

)

GENERATOR <1

~ HATCH t/)

~

EQUIPMENT HAT C K

<1 # =DOSE RATE

@ =SMEAR LOCATION DOSE RATES IN MRIHR

VBWR BASEMENT AREA REACTOR HEAD E_ CONTACT

.a_@ 30CM

  1. =DOSE RATE

=SMEAR LOCATION DOSE RATES IN MRIHR

Attachment to Survey D-055: VBWR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument: Tennelec XLB System A Analyzed By:

Serial No.: 2972-2 Signature:

Calibration Date: 1 Mar 2019 Reviewed:

Beta Efficiency: 33.47% Beta MDA: 16.9 dpm Alpha Efficiency: 36.28% Alpha MDA: 10.5 dpm Sample Date: 6/18/19 Count Date: 6/18/19 Alpha Alpha Beta Beta Level Location (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm 2 )

2 2 (DPM/100 cm 2 )

1 0 0 108.2 323 2 0 0 47.2 141 3 0 0 44.2 132 4 0 0 79.2 237 5 0 0 43.2 129 6 0 0 49.2 147 Main Floor 7 0.9 2.5 33.2 99.2 Levell 8 0 0 37.2 111 9 0 0 24.2 72.3 10 0.9 2.5 27.2 81.3 11 0 0 89.2 266 12 0 0 51.2 153 13 0 0 28.2 84.2 1 0.9 2.5 95.2 284 2 0 0 28.2 84.2 Rx Head 3 0 0 23.2 69.3 Level 4 (Bricks) 0 0 23.2 69.3 5 (Diamond Plate) 0.9 2.5 104.2 311 1 2.9 8.0 1944.2 5810 2 0 0 579.2 1730 3 0 0 701.2 2090 4 0 0 532.2 1590 Basement 5 0 0 691.2 2060 6 2.9 8.0 738.2 2210 7 (Sump Cover) 0 0 399.2 1190 8 (By Sump) 1.9 5.2 915 .. 2 2730 Page 1 of 1

VBWR & EVESR SITE MAP 7 8 0 0 7 CONCRETE PAD 9

MOCKUP AREA 8

10 9

8

© II 9

8 8

BUILDING

\QQQj I 1 12 10 EVESR 14 12 18 6 16 12 20 22 BUILDING TANKO PAD 30 32 68 60 118 90 1000 425 80 410 180

  1. :DOSE RATE DOSE RATES IN MICROREM/HR

ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial 1 Hour Decay >24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E-10 792.30 3.77E-10 103.39 4.53E-11 233.50 1.11E-10 0.00 O.OOE+OO 7.00 3.33E-12 Basement 2.83E+06 820.19 3.60E-10 1991.90 9.47E-10 260.29 1.14E-10 592.20 2.81E-10 0.49 2.15E-13 21.50 1.02E-11 Fuel Pool 2.83E+06 679.59 2.98E-10 1813.90 8.62E-10 71.89 3.15E-11 159.20 7.57E-11 1.09 4.78E-13 10.30 4.90E-12 EVESR First Floor 2.83E+06 3227.29 1.42E-09 7953.80 3.78E-09 718.89 3.15E-10 1551.40 7.37E-10 0.29 1.27E-13 5.20 2.47E-12 Basement 2.83E+06 4923.19 2.16E-09 11385.50 5.41E-09 999.79 4.38E-10 2181.90 1.04E-09 2.49 1.09E-12 75.60 3.59E-11 519' Level 2.83E+06 6876.69 3.02E-09 16930.10 8.05E-09 1534.89 6.73E-10 3353.20 1.59E-09 1.09 4.78E-13 59.90 2.85E-11 GETR First Floor 2.83E+06 190.09 8.33E-11 548.50 2.61E-10 71.99 3.16E-11 170.30 8.09E-11 1.29 5.66E-13 8.00 3.80E-12 Basement 2.83E+06 99.59 4.37E-11 245.00 1.16E-10 29.29 1.28E-11 76.60 3.64E-11 1.09 4.78E-13 15.00 7.13E-12 Third Floor 2.83E+06 124.29 5.45E-11 458.30 2.18E-10 43.29 1.90E-11 238.00 1.13E-10 0.79 3.46E-13 43.30 2.06E-11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%

Beta Efficiency 33.47%

dpm/uCi 2.22E+06 Alpha cpm/uCi 8.05E+05 Beta cpm/uCi 7.43E+05 Sampling Information Flow Initial 1 Hr A~~rox.

Minutes Rate Total Total Sam~le Count Count Minutes Half-Life Reactor Location Date Sam~led Time On Time Off sam~led (cfm) Flow {fe} ml/fe Volume {ml} Time Time Decay {min.}

VBWR First Floor 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:54 9:52 58 34.3 VBWR Basement 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:42 9:42 60 36.2 VBWR Fuel Pool 6/25/2019 9:43 10:03 20 5 100.0 28317 2.83E+06 10:16 12:10 114 35.2 EVESR First Floor 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:39 11:55 76 35.1 EVESR Basement 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:49 12:05 76 33.0 EVESR 519' Level 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:28 11:44 76 35.1 GETR First Floor 6/17/2019 14:17 14:37 20 5 100.0 28317 2.83E+06 14:45 15:49 64 45.7 GETR Basement 6/17/2019 9:50 10:10 20 5 100.0 28317 2.83E+06 10:58 12:00 62 35.1 GETR Third Floor 6/25/2019 8:55 9:15 20 5 100.0 28317 2.83E+06 9:36 10:36 60 39.4

  • HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 52 FOR THE YEAR 2019 LICENSE DR-10 DOCKET 50-183 MARCH 2020

EVESR Annual Report No. 52 ESADA-Vallecitos Experimental Superheat Reactor (Deactivated)

ANNUAL REPORT NO. 52 GE Hitachi Nuclear Energy (GEH) has maintained the ESADA Vallecitos Experimental Superheat Reactor (EVESR) in a deactivated status under the authority of Amendment No.7 to License DR-10, Docket 50-183, issued December 1, 2008. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented, as required by Amendment 7, Appendix A, Technical Specifications, section C. 1.

1.0

SUMMARY

Component removal activities began in 2008 above the 549-foot level. Tech Spec changes issued in Amendment 7 December 1, 2008 authorize the removal of systems beside the reactor vessel and bio-shield below the 549-level. Component removal concluded (current scope) in 2010. Entry into the containment building was made for routine radiation surveys and a general examination of conditions throughout the building. In accordance with written procedures, the Facility Manager controls access to the containment building.

Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review.

2.0 STATUS OF FACILITY The facility continues to be in deactivated status. The plugs to the reactor vessel and head storage shield, the wooden cover over the fuel storage pool remain in place.

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

An assessment for radionuclide distribution was performed of the shutdown reactors.

An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.

Page 1 of 3

EVESR Annual Report No. 52 3.1 GROUND WATER MONITORING WELL Groundwater well MW-9 was installed southwest of the EVESR and VBWR shutdown reactors. Monitoring Well 9 has two sampling points documented as MW-9S and MW-9D. These wells will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of the shutdown reactors in this area. The installation of these wells is part of the response letter to the NRC, "NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules", GEH Response Summary Dated May 31, 2019. Analytical results of groundwater samples collected from the wells during the reporting periods. These wells were sampled quarterly after installation in 2019.

Well W-9S (4S-1 E2P1)

Month Gross Alpha Gross Beta Tritium (pCi!L) (pCi!L) (pCi!L)

July 2019 2.81 1.62 0 October 2019 2.31 2.82 176 Annual Average 2.56 2.22 88 Well W-9D (4S-1 E2P2)

Month Gross Alpha Gross Beta Tritium (pCi!L) (pCi!L) (pCi!L)

July 2019 5.04 2.29 395 October 2019 4.10 0.75 270 Annual Average 4.57 1.52 333 4.0 ACTIVITIES Routine inspections were conducted during this report period. During this report period, two additional monitoring wells were installed downgradient of EVESR. No major activities occurred inside the reactor during this period.

5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The EVESR Facility Manager remains K. P.

Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.

6.0 CONCLUSION

GE Hitachi Nuclear Energy concludes that the deactivated ESADA-Vallecitos Experimental Superheat Reactor is being maintained in a safe shutdown condition. The Page 2 of 3

EVESR Annual Report No. 52 inspections, access control, and administratively controlled activities ensure maximum protection for the public health and safety. The procedures will be continued to maintain thi I high level of protection.

GE Hitachi Nuclear Energy Vallecitos Operations I

Manager Vallecitos Nuclear Center Page 3 of 3

SURVEYOR (print and sign) IREVIEWER NO.

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

D-056 06/18/19 TIME:

NUCLEAR SAFETY SURVEY RECORD EVESR Containment 1100 IRl Routine REASON D Special Annual Survey (Revision 1) Dated 12/15/2020 . Edits to Revision 1 shown in red ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item ~ y n TOTAL Distance ~y ~y a. a. ~y ~y a. a.

No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 487' Level (Basement) <l <l F 2 503' Level <l <l F 3 519' Level <l <l F 4 534' Level -General Area 1.5 1.5 F 5 - Floor Drain 7 7 c 6 - Floor Drain @ l' 1.5 1.5 l' 7 - Emergency Cooling Valves 4.5 4.5 F 8

9 549' Level <l <l F 10 Equipment Air Lock <l <l F 11 Personnel Air Lock <l <l F 12 Top of Spent Fuel Pool (Main Floor) <0.5 <0.5 F 13 14 15 16 INSTRUMENT USED Tennelec PRM-7 CP-5 RO -20 PNR-4 TBM- E -120 RM -14 RM- 15 PAC -1SA LUDLUM-12 SERIAL NUMBER 2972-1 6128 Area Posted: (circle applicable) RA HRA (CA ~ M9 AIRBORNE PROBE a AC- 3A (U) 10% PROBE ~y PANCAKE 20%

COMMENTS Smears completed on Tennelec see attachment EFF. a 43-4 (U) 10% EFF.

Areas smeared are on maps with attachment (4 p (4 p GEO.) GEO.)

NEO 289 (REV. 07/10)

EVESR 549' LEVEL

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EVESR 500' LEVEL IN-CORE FLUX AREA CJ

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Attachment to Survey D-056: EVESR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument: Tennelec XLB System A Analyzed By: Names on Originals on site Serial No.: 2972-2 Signature: Names on Originals on site Calibration Date: 1 Mar 2019 Reviewed: Names on Originals on site Beta Efficiency: 33.47% Beta MDA: 16.9 dpm Alpha Efficiency: 36.28% Alpha MDA: 10.5 dpm Sample Date: 6/18/19 Count Date: 6/18/19 Alpha Alpha Beta Beta Level Location (NCPM/100 cm 2 ) (DPM/100 cm 2 ) (NCPM/100 cm 2 ) (DPM/100 cm 2 )

1 0 0 17.2 51.4 2 0 0 17.2 51.4 3 0 0 12.2 36.4 4 0.9 2.5 16.2 48.4 5 0.9 2.5 20.2 60.3 549' 6 0 0 8.2 24.5 Levell 7 0 0 10.2 30.5 8 0 0 12.2 36.4 9 0 0 14.2 42.4 10 0 0 18.2 18.2 11 1.9 5.2 37.2 37.2 1 0 0 120.2 359 2 0 0 153.2 458 3 0 0 482.2 1440 4 0 0 207.2 619 534' 5 1.9 5.2 110.2 329 Level 2 6 0 0 95.2 284 7 0 0 176.2 526 8 0 0 36.2 108 9 0.9 2.5 108.2 323 10 (Fenced Area) 0.9 2.5 110.2 329 1 0 0 71.2 213 519' 2 0 0 43.2 129 Level3 3 0.9 2.5 76.2 228 4 0.9 2.5 189.2 565 Page 1 of 2

Attachment to Survey D-056: EVESR Containment Annual Survey Smear Results Alpha Alpha Beta Beta Level Location (NCPM/100 cm 2 ) (DPM/100 cm 2 ) (NCPM/100 cm 2 ) (DPM/100 cm 2 )

5 0 0 77.2 231 6 0 0 48.2 144 1 0 0 111.2 332 2 0 0 883.2 2,640 3 2.89 8.0 124.2 371 503' 4 0 0 78.2 234 Level4 5 0 0 129.2 386 6 0 0 193.2 577 7 0 0 95.2 284 8 0.89 2.5 281.2 840 1 0 0 144.2 431 500' 2 0 0 23.2 69.3 In-Core 3 0 0 298.2 891 Flux Level 4 0 0 3650 10,900 1 0 0 106.2 317 2 0 0 326.2 975 3 1.89 5.2 130.2 389 4 1.89 5.2 140.2 419 5 0 0 47.2 141 487' 6 0 0 68.2 204 Basement 7 0 0 118.2 353 8 0 0 244.2 730 9 0 0 210.2 628 10 0.89 2.5 335.2 1000 11 0.89 2.5 470.2 1400 Page 2 of 2

VBWR & EVESR SITE MAP 7 8 0 0 7 CONCRETE PAD 9

MOCKUP AREA 8

10 9

8

© II 9

8 8

BUILDING

\QQQj I 1 12 10 EVESR 14 12 18 6 16 12 20 22 BUILDING TANKO PAD 30 32 68 60 118 90 1000 425 80 410 180

  1. :DOSE RATE DOSE RATES IN MICROREM/HR

ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial 1 Hour Decay >24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E-10 792.30 3.77E-10 103.39 4.53E-11 233.50 1.11E-10 0.00 O.OOE+OO 7.00 3.33E-12 Basement 2.83E+06 820.19 3.60E-10 1991.90 9.47E-10 260.29 1.14E-10 592.20 2.81E-10 0.49 2.15E-13 21.50 1.02E-11 Fuel Pool 2.83E+06 679.59 2.98E-10 1813.90 8.62E-10 71.89 3.15E-11 159.20 7.57E-11 1.09 4.78E-13 10.30 4.90E-12 EVESR First Floor 2.83E+06 3227.29 1.42E-09 7953.80 3.78E-09 718.89 3.15E-10 1551.40 7.37E-10 0.29 1.27E-13 5.20 2.47E-12 Basement 2.83E+06 4923.19 2.16E-09 11385.50 5.41E-09 999.79 4.38E-10 2181.90 1.04E-09 2.49 1.09E-12 75.60 3.59E-11 519' Level 2.83E+06 6876.69 3.02E-09 16930.10 8.05E-09 1534.89 6.73E-10 3353.20 1.59E-09 1.09 4.78E-13 59.90 2.85E-11 GETR First Floor 2.83E+06 190.09 8.33E-11 548.50 2.61E-10 71.99 3.16E-11 170.30 8.09E-11 1.29 5.66E-13 8.00 3.80E-12 Basement 2.83E+06 99.59 4.37E-11 245.00 1.16E-10 29.29 1.28E-11 76.60 3.64E-11 1.09 4.78E-13 15.00 7.13E-12 Third Floor 2.83E+06 124.29 5.45E-11 458.30 2.18E-10 43.29 1.90E-11 238.00 1.13E-10 0.79 3.46E-13 43.30 2.06E-11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%

Beta Efficiency 33.47%

dpm/uCi 2.22E+06 Alpha cpm/uCi 8.05E+05 Beta cpm/uCi 7.43E+05 Sampling Information Flow Initial 1 Hr A~~rox.

Minutes Rate Total Total Sam~le Count Count Minutes Half-Life Reactor Location Date Sam~led Time On Time Off sam~led (cfm) Flow {fe} ml/fe Volume {ml} Time Time Decay {min.}

VBWR First Floor 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:54 9:52 58 34.3 VBWR Basement 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:42 9:42 60 36.2 VBWR Fuel Pool 6/25/2019 9:43 10:03 20 5 100.0 28317 2.83E+06 10:16 12:10 114 35.2 EVESR First Floor 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:39 11:55 76 35.1 EVESR Basement 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:49 12:05 76 33.0 EVESR 519' Level 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:28 11:44 76 35.1 GETR First Floor 6/17/2019 14:17 14:37 20 5 100.0 28317 2.83E+06 14:45 15:49 64 45.7 GETR Basement 6/17/2019 9:50 10:10 20 5 100.0 28317 2.83E+06 10:58 12:00 62 35.1 GETR Third Floor 6/25/2019 8:55 9:15 20 5 100.0 28317 2.83E+06 9:36 10:36 60 39.4

  • HITACHI GE Hitachi Nuclear Energy Vallecitos Nuclear Center Sunol, California GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 61 FOR THE YEAR 2020 LICENSE TR-1 DOCKET 50-70 MARCH 2020

GETR Annual Report No. 61 General Electric Test Reactor (Deactivated)

ANNUAL REPORT NO. 61 GE Hitachi (GEH) has maintained the General Electric Test Reactor (GETR) in a deactivated status under the authority of Amendment No. 17 to License TR-1, Docket 50-70, issued October 22, 2007, as specified in TS 6.6.1 to Amendment No. 14, issued February 5, 1986. In this annual report, a summary of the status of the facility for the period of January 1, 2019, to December 31, 2019, is presented.

1.0

SUMMARY

The facility remains in essentially the same condition described in Annual Report No. 60.

Entry into the reactor building was made for routine radiation surveys and a general examination of conditions throughout the building. The crane, elevator, and ventilation were serviced and tested in 2011 in anticipation of beginning remediation activities.

Such activities have not begun.

Radiation and contamination levels remain at acceptable levels.

2.0 STATUS OF FACILITY In accordance with written procedures, the Facility Manager controls access to the containment building and general systems. The facility continues to be in deactivated status. There were no changes authorized by the Facility Manager pursuant to 10CFR50.59(a) in 2019.

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

Radiological surveys were performed in June 2019, in unknown areas that had not been surveyed previously using Change Authorization 19-05. Entries into these areas was Page 1 of 4

GETR Annual Report No. 61 performed using SCBA and full-face respiratory protection. Radiological surveys are available for review at VNC. Some of the areas were found to have high radiation levels and high levels of contamination. Areas were posted as required by regulation based on survey resu Its.

An assessment for radionuclide distribution was performed of the shutdown reactors.

An external consultant performed the Updated Radiological Source Term for the Vallecitos Nuclear Center. The assessment has been submitted to the NRC for review and is available for further review at VNC if needed.

3.1 GETR Stack Although maintenance was performed on the stack in 2011, and the stack was tested, there has been no remediation effort performed for the GETR reactor. The ventilation system is operational, but not currently in use.

GETR Stack was operational from June to November 2019, during entries made into unknown areas for surveying purposes. The data listed below is from the GETR stack.

GETR Stack Month Beta (uCi) Alpha (uCi)

May 2019 0.00 1.77E-02 June 2019 3.48E-03 3.67E-01 July 2019 1.39E-03 6.36E-02 August 2019 7.33E-03 5.59E-01 September 2019 6.57E-03 1.78E-01 October 2019 5.74E-03 1.14E-01 November 2019 6.91 E-03 1.73E-01 Total (Annual) 3.14E-02 1.47E+OO 3.2 Gamma Radiation The yearly dose results for the year 2019 as determined from evaluation of site perimeter environmental monitoring dosimeters showed no departure from normal stable backgrounds.

3.3 Vegetation No alpha, beta or gamma activity attributable to activities at the GETR facility was found on or in vegetation in the vicinity of the site.

Page 2 of 4

GETR Annual Report No. 61 3.4 Ground Water Monitoring Well Data Analytical results of groundwater samples collected from the B-2 (GETR) well during the reporting periods. The GETR well was sampled quarterly in 2019. During the fourth quarter sampling period, a sample was not collected from the B-2 well due to a blockage caused by the sampling bag. Condition Report# 33068 was entered into the Condition Report System.

GETR Well B-2 Month Gross Gross Beta Tritium Alpha (pCi!L) (pCi!L)

(pCi!L)

January 2019 9.36 2.76 522 April2019 3.93 3.24 149 August 2019 6.50 2.47 318 November 2019 No Sample Collected CR # 33068 Groundwater well MW-8 was installed southwest of the GETR shutdown reactor. The well will provide additional groundwater monitoring of the hydrogeologic conditions downgradient of GETR. The installation of the well is part of the response letter to the NRC, "NRC Request for Additional Information Related to Vallecitos Nuclear Center (VNC) Request for Alternate Decommissioning Schedules", GEH Response Summary Dated May 31, 2019. Well was sampled quarterly in 2019 after installation.

Well W-8 (4S-1 E2M01)

Month Gross Alpha Gross Beta Tritium (pCi!L) (pCi!L) (pCi!L)

July 2019 6.86 1.51 371 October 2019 1.32 2.28 798 Annual Average 4.09 1.90 585 4.0 ACTIVITIES Routine inspections were conducted during this report period. A small amount of water

(<5 gallon) was identified in the elevator sump area of GETR. The water was removed (CR# 31626), and gamma spectroscopy was performed. Results were normal. There were no preventive or corrective maintenance activities performed having safety significance during the reporting period.

5.0 ORGANIZATION The Site Manager remains M. J. Feyrer. The GETR Facility Manager remains K. P.

Zanotto. The Manager, Regulatory Compliance and EHS remains J. Smyly.

Page 3 of 4

GETR Annual Report No. 61

6.0 CONCLUSION

GE Hitachi Nuclear Energy concludes that the deactivated GETR is being maintained in a safe shutdown condition . The inspections, access control, and 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 3~

Manager Vallecitos Nuclear Center Page 4 of4

SURVEYOR (print and sign) IREVIEWER NO.

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

C-020 06/17/19 TIME:

NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 1 of 2) 1100 IRl Routine REASON D Special Annual Survey (Revision 1) Dated 12/15/2020 . Edits to Revision 1 shown in red ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item ~ y n TOTAL Distance ~y ~y a. a. ~y ~y a. a.

No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 Personnel Air Lock <l <l F 2 Equipment Air Lock <l <l F 3 Personnel Air Lock SOP <l <l F 4 l st Floor - Clean Area <l <l F 5 -Zone Area <l <l F 6 2nd Floor - General Dose Rate <l <l F 7 - EEHS Cubicle Door 7 7 c 8 - Field Reading Around EEHS Cubicle 5 5 F 9 - Filter Bank <l <l c 10 - Filter Bank downstairs 5 5 F 11 3rd Floor- Zone Area North 1.5 1.5 F 12 - Zone Area South l l F 13 -Bridge 1.5 1.5 F 14 - Missile Shield <l <l F 15 -Platform <l <l F 16 -Clean Area <l <l F INSTRUMENT USED Tennelec PRM-7 CP- 5 R0-20 PNR-4 TBM- E- 120 RM -14 RM -15 PAC- lSA LUDLUM-12 SERIAL NUMBER 2972-1 6128 Area Posted: (circle applicable) RA HRA ~A) ~ AIRBORNE PROBE a AC-3A (U) 10% PROBE bg PANCAKE 20%

COMMENTS Smears completed on Tennelec see attachment EFF a 43- 4 (U) 10% EFF Areas smeared are on maps with attachment (4P (4P GEO.) GEO.)

NEO 289 (REV. 07/10)

SURVEYOR (print and sign) IREVIEWER NO.

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

C-020 06/17/19 TIME:

NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of 2) 1100 X Routine REASON 0 Special Annual Survey (Revision 1) Dated 12/15/2020. Edits to Revision 1 shown in red ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item b g n TOTAL Distance bg bg a a bg bg a a No. rnRad!h rnR!h rnRern!h rnRern!h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 3rd Floor- Zone Area Floor Drain 6 6 c 2 Elevator <1 <1 F 3 Basement - Clean Area <1 <1 F 4 - Filter Bank <1 <1 F 5 -Zone Area 3 3 F 6 - Control Rod Storage <1 <1 c 7 - Control Rod Repair Hood <1 <1 c 8 -Autoclave 2 2 c 9 Mezzanine between 2nd & 3rd Floors <1 <1 F 10 B-1 Basement General Area 5 5 F 11 B-1 Basement Pipe 120 120 c 12 B-1 Basement Pipe @ 1' 15 15 1' 13 B-2/B Basement General Area <1 <1 F 14 B-3 Basement General Area <1 <1 F 15 Heat Exchange 25 25 c 16 Heat Exchange Room General Area <1 <1 F INSTRUMENT USED Tennelec PRM-7 CP- 5 R0-20 PNR-4 TBM- E- 120 RM- 14 RM- 15 PAC- 1SA LUDLUM-12 SERIAL NUMBER 2972-1 6128 Area Posted: (circle applicable) RA HRA ~A)~ ~) AIRBORNE PROBE a AC-3A (U) 10% PROBE bg PANCAKE 20%

COMMENTS Smears completed on Tennelec see attachment EFF a 43- 4 (U) 10% EFF Areas smeared are on maps with attachment (4P (4P GEO.) GEO.)

NEO 289 (REV. 07/10)

GETR Basement

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Attachment to Survey C-020: GETR Containment Annual Survey Smear Results Name and signature on original at GEH Vallecitos Nuclear Center Instrument: Tennelec XLB System A Analyzed By: Names on Originals on site Serial No.: 2972-2 Signature: Names on Originals on site Calibration Date: 1 Mar 2019 Reviewed: Names on Originals on site Beta Efficiency: 33.47% Beta MDA: 16.9 dpm Alpha Efficiency: 36.28% Alpha MDA: 10.5 dpm Sample Date: 6/17/19 Count Date: 6/17/19 Alpha Alpha Beta Beta Level Location (NCPM/100 cm 2 ) (DPM/100 cm 2 ) (NCPM/100 cm 2 ) (DPM/100 cm 2 )

1 (Zone Floor) 0.9 2.5 72 216 2 (Zone Floor) 0.9 2.5 63 189 3 (Zone Floor) 0.0 0.0 335 1,001 4 (Zone Flats) 0.9 2.5 42 126 5 (Zone Flats) 0.0 0.0 24 72 6 (Zone Floor - Left of SOP) 0.0 0.0 598 1,787 Main 7 (Zone Floor - Right of SOP) 0.0 0.0 340 1,016 Floor 8 (By Ladder) 0.0 0.0 1,075 3,212 Level 1 Flats behind GE Logo 0.0 0.0 17 51 Floor Behind GE Logo 0.9 2.5 67 201 CA Area Floor Near Entrance 0.0 0.0 15 45 Equipment Air Lock 0.0 0.0 1 4 Clean Floor Near Entrance 0.9 2.5 26 78 Personnel Air Lock SOP 0.0 0.0 1 4 Zone Area CRD Rack 0.0 0.0 61 183 Zone Area Table 0.9 2.5 35 105 HeatExchanger(HX)Room 0.0 0.0 25 75 Elevator 0.9 2.5 32 96 Clean Area 0.0 0.0 17 51 Basement Zone Area Rod Repair Hood 3.9 10.7 12,174 36,373 Zone Area Floor 0.0 0.0 548 1,638 Room B-3 Flats 0.0 0.0 151 452 Room B-3 Floor 0.0 0.0 42 126 Room B-3 Floor @ Door 0.9 2.5 925 2,764 Under Vessel - Flats 1.9 5.2 75 225 Page 1 of 3

Attachment to Survey C-020: GETR Containment Annual Survey Smear Results Alpha Alpha Beta Beta Level Location (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm ) (DPM/100 cm 2 )

2 2 2 Under Vessel- Floor 0.9 2.5 157 470 Under Vessel - Rust Floor 0.0 0.0 1,322 3,950 Basement: Under HX Room 0.9 2.5 59 177 HX Room Lead Shield 0.9 2.5 21 63 HX Room Flats/Pipes 0.9 2.5 54 162 Basement Pump Room (B-1) 0.0 0.0 117 350 Pump Room (B-1) Floor 0.0 0.0 60 180 Pump Room (B-1) Flats 0.0 0.0 64 192 Pump Room (B-1) Floor 0.0 0.0 60 180 Inside, Only Entrance Hot Spot 0.0 0.0 2,917 8,716 Only Entrance Pump 0.0 0.0 261 780 Only Entrance Drain 0.0 0.0 2,575 7,694 Elevator 0.9 2.5 11 33 1 0.0 0.0 3 10 Level 2 2 0.0 0.0 6 19 3 0.0 0.0 31 93 4 (@Stairs) 0.9 2.5 41 123 5 0.9 2.5 47 141 6 (@ Back Stairs Area) 0.9 2.5 34 102 Room 1 Floor 0.9 2.5 138 413 Room 1 Flats 1.9 5.2 157 470 Level 2.5 General Area 1 1.9 5.2 11 33 Mezzanine General Area 2 1.9 5.2 18 54 General Area 3 0.0 0.0 32 96 Top of Bathroom 0.9 2.5 39 117 Under Platform #1 Floor 0.9 2.5 39 117 Under Platform #2 Floor 0.0 0.0 129 386 Floor (1) @ Stairs 0.0 0.0 100 299 Floor (2) Left of Stairs 0.0 0.0 26 78 Floor (3)@ Bathroom 0.0 0.0 50 150 Level 3 Floor (4)@ Elevator 0.0 0.0 36 108 Top Floor Floor (5) @ Platform Stairs 0.9 2.5 135 404 Floor (6) Left of Missile Shield 0.0 0.0 354 1,058 Floor (7) Left side of Cavity 0.0 0.0 444 1,327 Floor (8) Right of Missile Shield 0.0 0.0 211 631 Floor (9) Right of Cavity 0.0 0.0 2,944 8,797 Floor (10) By Straight Ladder 0.0 0.0 1,083 3,236 Page 2 of 3

Attachment to Survey C-020: GETR Containment Annual Survey Smear Results Alpha Alpha Beta Beta Level Location (NCPM/100 cm ) (DPM/100 cm ) (NCPM/100 cm ) (DPM/100 cm 2 )

2 2 2 Missile Shield (11) 0.0 0.0 147 440 Upper Deck (12) 0.9 2.5 24 72 Upper Deck (13) 2.9 8.0 48 144 Upper Deck (14) 0.0 0.0 32 96 Level 3 Flats (15) 0.0 0.0 23 69 Top Floor Flats (16) 3.9 10.7 127 380 Bridge (17) 0.9 2.5 234 700 Flats- Spreader Bar (18) 0.9 2.5 131 392 Alpha Alpha Beta Beta Level Location (NCPM) (DPM) (NCPM) (DPM)

EEHS Floor- 1 76.9 211.9 334207 998527 EEHS Floor- 2 21.9 60.3 31243 93346 EEHS Floor- 3 3.9 10.7 73920 220855 EEHS Flats- 1 5.9 16.2 36608 109376 Level 2 EEHS Flats- 2 0.9 2.5 24.2 72.3 EEHS Flats- 3 7.9 21.7 9786 29238 EEHS Flats- 4 0.9 2.5 2370 7081 EEHS Flats- 5 9.9 27.3 29546 88276 Note: The smears in the Experiment Effluent Hold-up System (EEHS) room were taken with disk smears, but were not limited to 100 cm 2

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GETR SITE MAP

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BUILDING 40 60 24 14 30 20 25 32 GETR 25 36 50 60

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47 oG 300 a2800

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1200 600

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  1. = DOSE RATE 14 20 DOSE RATES IN MICROREM/HR 17

ATTACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial 1 Hour Decay >24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E-10 792.30 3.77E-10 103.39 4.53E-11 233.50 1.11E-10 0.00 O.OOE+OO 7.00 3.33E-12 Basement 2.83E+06 820.19 3.60E-10 1991.90 9.47E-10 260.29 1.14E-10 592.20 2.81E-10 0.49 2.15E-13 21.50 1.02E-11 Fuel Pool 2.83E+06 679.59 2.98E-10 1813.90 8.62E-10 71.89 3.15E-11 159.20 7.57E-11 1.09 4.78E-13 10.30 4.90E-12 EVESR First Floor 2.83E+06 3227.29 1.42E-09 7953.80 3.78E-09 718.89 3.15E-10 1551.40 7.37E-10 0.29 1.27E-13 5.20 2.47E-12 Basement 2.83E+06 4923.19 2.16E-09 11385.50 5.41E-09 999.79 4.38E-10 2181.90 1.04E-09 2.49 1.09E-12 75.60 3.59E-11 519' Level 2.83E+06 6876.69 3.02E-09 16930.10 8.05E-09 1534.89 6.73E-10 3353.20 1.59E-09 1.09 4.78E-13 59.90 2.85E-11 GETR First Floor 2.83E+06 190.09 8.33E-11 548.50 2.61E-10 71.99 3.16E-11 170.30 8.09E-11 1.29 5.66E-13 8.00 3.80E-12 Basement 2.83E+06 99.59 4.37E-11 245.00 1.16E-10 29.29 1.28E-11 76.60 3.64E-11 1.09 4.78E-13 15.00 7.13E-12 Third Floor 2.83E+06 124.29 5.45E-11 458.30 2.18E-10 43.29 1.90E-11 238.00 1.13E-10 0.79 3.46E-13 43.30 2.06E-11 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%

Beta Efficiency 33.47%

dpm/uCi 2.22E+06 Alpha cpm/uCi 8.05E+05 Beta cpm/uCi 7.43E+05 Sampling Information Flow Initial 1 Hr A~~rox.

Minutes Rate Total Total Sam~le Count Count Minutes Half-Life Reactor Location Date Sam~led Time On Time Off sam~led (cfm) Flow {fe} ml/fe Volume {ml} Time Time Decay {min.}

VBWR First Floor 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:54 9:52 58 34.3 VBWR Basement 6/18/2019 7:47 8:07 20 5 100.0 28317 2.83E+06 8:42 9:42 60 36.2 VBWR Fuel Pool 6/25/2019 9:43 10:03 20 5 100.0 28317 2.83E+06 10:16 12:10 114 35.2 EVESR First Floor 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:39 11:55 76 35.1 EVESR Basement 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:49 12:05 76 33.0 EVESR 519' Level 6/18/2019 9:34 9:54 20 5 100.0 28317 2.83E+06 10:28 11:44 76 35.1 GETR First Floor 6/17/2019 14:17 14:37 20 5 100.0 28317 2.83E+06 14:45 15:49 64 45.7 GETR Basement 6/17/2019 9:50 10:10 20 5 100.0 28317 2.83E+06 10:58 12:00 62 35.1 GETR Third Floor 6/25/2019 8:55 9:15 20 5 100.0 28317 2.83E+06 9:36 10:36 60 39.4

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