M180129, GE-Hitachi Nuclear Energy Americas, LLC - Annual Shutdown Reactor Report Supplement for the Year 2017: Difference between revisions

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{{#Wiki_filter:* HITACHI M180129 June 20 , 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001 GE Hitachi Nuclear Energy Matt 1. Feyrer Site Manager, vallecitos Nuclear Center 6705 Vallecitos Rd Sunol, CA 94586 USA T 925 918 6018 Matt.feyrer@ge.com  
{{#Wiki_filter:*           HITACHI                                             GE Hitachi Nuclear Energy Matt 1. Feyrer Site Manager, vallecitos Nuclear Center 6705 Vallecitos Rd Sunol, CA 94586 USA M180129                                                        T 925 918 6018 Matt.feyrer@ge.com June 20, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001


==Subject:==
==Subject:==
GEH Annual Shutdown Reactor Report Supplement for the Year 2017 References
GEH Annual Shutdown Reactor Report Supplement for the Year 2017
: 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 Control Desk "GEH Annual Shutdown Reactor Reports for the Year 2017, 3/29/18 Enclosed is a supplement to the 2018 Annual Report (Reference  
 
: 2) for the deactivated Vallecitos Boiling Water Reactor (VBWR}, located at the GE Hitachi, Vallecitos Nuclear Center near Sunol, California.
==References:==
If there are any questions or additional information is required, please contact me at the number above. Matt Feyrer, Site Manager Vallecitos Nuclear Center  
: 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 Control Desk "GEH Annual Shutdown Reactor Reports for the Year 2017, 3/29/18 Enclosed is a supplement to the 2018 Annual Report (Reference 2) for the deactivated Vallecitos Boiling Water Reactor (VBWR}, located at the GE Hitachi, Vallecitos Nuclear Center near Sunol, California.
If there are any questions or additional information is required, please contact me at the number above.
Matt Feyrer, Site Manager Vallecitos Nuclear Center


==Enclosure:==
==Enclosure:==
VBWR Annual Report No. 53, Supplement dated June 2018 cc: NRC Region IV Administrator J. Parrott, NRC NMSS MJF 18-007
( . HITACHI Vallecitos Nuclear Center Sunol, Collfarnio VALLECITOS BOILING WATER REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 53 FOR THE YEAR 2017 LICENSE DPR-1 DOCKET 50-18 June 2018


VBWR Annual Report No. 53, Supplement dated June 2018 cc: NRC Region IV Administrator J. Parrott, NRC NMSS MJF 18-007 
Vallecitos Boiling Water Reactor (Deactivated}
(. HITACHI VALLECITOS BOILING WATER REACTOR (DEACTIVATED)
Annual Report No. 53 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWR) in a deactivated status under the authority of Amendment No. 21 to license DPR-1, Docket 50-18, issued Oct 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2.017 to December 31, 2017 is presented, as required by paragraph S.d.2 of the license.
ANNUAL REPORT NO. 53 FOR THE YEAR 2017 LICENSE DPR-1 DOCKET 50-18 June 2018 Vallecitos Nuclear Center Sunol, Co llfarni o Vallecitos Boiling Water Reactor (Deactivated}
1.0  
Annual Report No. 53 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWR) in a deactivated status under the authority of Amendment No. 21 to license DPR-1, Docket 50-18, issued Oct 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2.017 to December 31, 2017 is presented, as required by paragraph S.d.2 of the license. 1.0  


==SUMMARY==
==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 fadtity indicate that levels remain low. Results of the surveys are presented in attachment  
All reactor systems have been removed from the containment except for the reactor vessel.
: 1. Air sampling results are presented in attachment  
The water level within the reactor vessel was monitored and has remained essentially constant throughout the report period.
: 2. The radiation/contamination levels listed are representative but not necessarily maximum values. During the 2017 annual inspection in December a small volume of water was found in the basement of the VBWR containment.
Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review.
Due to this volume of water, no direct surveys or smears were taken in this particular area. In April, another entry was made to re-inspect the area. As water was still present, a sample was taken for analysis wiU1 the results attached below. In Page 1 of3 VBWR Annual Rec:ton No. 53 addition.
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.
CR#28719 was initiated to track this issue to resolution.
3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the fadtity indicate that levels remain low.
Action items include removing water from the containment basement as well as a formal evaluation of how the water entered into this area. This evaluation is beginning in late June, early July. Month I Gross beta Gross Alpha ).l.Ci/ml l Tritium ).l.Ci/ml April2018 I 3.46E-07 8.66E-08 l <MDC Page 2 of 3 4.0 ACTIVITIES Routine inspections were conducted during this report period. No other significant activities occurred at VBWR. S.O ORGANIZATION The organizational structure remained unchanged during 2017. The Site Manager remains M. J. Feyrer. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS, T. M. leik, retired January 2018. J. G. Ayala is currently Acting Manager, Regulatory Compliance and EHS.  
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.
During the 2017 annual inspection in December a small volume of water was found in the basement of the VBWR containment. Due to this volume of water, no direct surveys or smears were taken in this particular area. In April, another entry was made to re-inspect the area. As water was still present, a sample was taken for analysis wiU1 the results attached below. In Page 1 of3
 
VBWR Annual Rec:ton No. 53 addition. CR#28719 was initiated to track this issue to resolution. Action items include removing water from the containment basement as well as a formal evaluation of how the water entered into this area. This evaluation is beginning in late June, early July.
Month         I Gross beta ~-tCi/ml    Gross Alpha ).l.Ci/ml l Tritium ).l.Ci/ml April2018       I       3.46E-07               8.66E-08       l       <MDC Page 2 of 3
 
4.0 ACTIVITIES Routine inspections were conducted during this report period. No other significant activities occurred at VBWR.
S.O ORGANIZATION The organizational structure remained unchanged during 2017. The Site Manager remains M. J.
Feyrer. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS, T. M. leik, retired January 2018. J. G. Ayala is currently Acting Manager, Regulatory Compliance and EHS.


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


GE Hitachi Nuclear Energy concludes that the deactivated VBWR is being maintained in a safe shutdown condition.
GE Hitachi Nuclear Energy concludes that the deactivated VBWR is being maintained in a safe shutdown condition. The inspections, access control, and administratively controlled activities ensure maximum protection for the public health (lnd safety. The procedures will be continued to maintain this high level of protection.
The inspections, access control, and administratively controlled activities ensure maximum protection for the public health (lnd safety. The procedures will be continued to maintain this high level of protection.
GE Hitachi Nuclear Energy Vallecitos Operations Page 3 of 3
GE Hitachi Nuclear Energy Vallecitos Operations Page 3 of 3 SURVEYOR (print and sign) I REVIEWER NO. e HITACHI Name and signatures on Original at GEH Vallecitos D-0105 LOCATION DATE: VALLECITOS NUCLEAR CENTER 12/09/17 NUCLEAR SAFETY SURVEY RECORD VBWR Containment TIME: 0930 liD Routine REASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item I> I n TOTAL Distance llr l\7 u u Jly Jlr tt a No. mRild/ll mll.lll mRemlh mRemlil CPM dPM CPM dPM CPM nPM CPM dPM AREA 1 Main Floor -General Area *1 < 1 F <100 <500 <20 <200 IOOcm: 2 -Area Over Reactor Vessel *J *: I F <100 <500 <20 <200 IOOcm* 3 4 Basement -General Area* 5 -Sump* 6 7 Reactor Vessel Head Area ! <I F <100 <500 <20 <200 100 8 9 Top of Fuel Pool I *:I F <100 <500 <20 <:\00 100 10 Personnel Air Lock . I , I F '100 <500 <20 11 < 200 100 12 13 Equipment Air Lock <I <I F <100 <500 <20 <200 IOOcm 14 15 16 INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM-E-120 RM-RM-PAC -1SA LUOLUM-12 SERIAL NUMBER 4549 1385 897 Area Posted: (circle applicable)
 
RA HRA CA RMA AIRBORNE PROBE u AC-3A (U} 10% X PROBE !lr PANCAKE 20% X OMMEmS
SURVEYOR (print and sign)                     IREVIEWER                      NO.
* No entry to basement due to raln water in basement.
e       HITACHI VALLECITOS NUCLEAR CENTER Name and signatures on Original at GEH Vallecitos LOCATION                                                                      DATE:
u 43-4 (U) 10% EFF EFF (4 p (4 p GEO! GEO.J NEO 289 (REV. 07/10)
D-0105 12/09/17 TIME:
ATTACHMENT2:
NUCLEAR SAFETY SURVEY RECORD                                             VBWR Containment                                                                 0930 liD Routine REASON 0 Special                 Annual Survey ITEMS OR LOCATION                                   DOSE RATE                         DIRECT READING                   SMEAR READINGS Item                                                   I>         I       n     TOTAL   Distance   llr     l\7     u       u       Jly       Jlr     tt     a No.                                               mRild/ll   mll.lll   mRemlh mRemlil             CPM     dPM     CPM     dPM     CPM       nPM     CPM     dPM     AREA 1 Main Floor - General Area                                 *1               < 1       F                                   <100       <500     <20   <200 IOOcm:
Air Sample Data for Vallecitos Reactor Annual Inspection 2017 Initial 1 Hour Decay 24/48 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 nwm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 1281.30 6.22E*l0 3323.20 1.68E-09 541.10 2.63E-10 1221.80 5.93E-10 2.80 1.36E*12 8.60 4.34E-12 Basement 2.83E+06 1562.70 7.59E*10 4024.50 2.03E-09 805.50 3.91E-10 1827.70 8.87E-10 0.60 2.91E-13 5.80 2.93E-12 Fuel Pool 2.83E+06 1826.10 8.87E-10 4696.60 2.37E-09 811.70 3.94E-10 1855.40 9.01E-10 1.10 5.34E-13 11.10 S.61E-12 EVESR First Floor 2.83E+06 5906.20 2.87E*09 16961.60 8.57E-09 2885.60 1.40E*09 6429.30 3.12E-09 2.30 1.12E-l2 5.00 2.53E-12 Basement 2.83E+06 4734.50 2.30E-09 12859.00 6.50E-09 2424.70 1.18E-09 5572.80 2.71E-09 1.20 5.83E-13 42.70 2.16E-11 519' Level 2.83E+06 4021.00 1.95E*09 10887.10 S.SOE-09 2119.60 1.03E..Q9 480.4.20 . 2.33E-09 1.60 7.77E-13 5.70 2.88E-12 GETR First Floor Z.83E+06 1689.80 8.21E-10 4508.90 2.18E-09 628.80 3.0SE-10 1397.40 6.79E-10 5.30 2.57E-12 15.50 7.83E-12 Basement 2.83E+06 1645.90 7.99E*10 4496.20 2.27E-09 764.30 3.71&#xa3;-10 1741.70 8.46&#xa3;-10 1.10 5.34E-13 17.00 8.59E-12 Third Floor 2.83E+06 1455.10 7.07E*10 3746.50 1.89&#xa3;-09 798.90 3.88E-10 1859.80 9.03&#xa3;-10 1.00 4.86E-13 23.70 1.20E-11 --------***********-*****--**---******---*-***-*-*----*---*------*-------*--
2   - Area Over Reactor Vessel                               *J               *: I       F                                   <100       <500     <20   <200     IOOcm*
-*--*-Tennelec System "B" Efficiency
3 4 Basement - General Area*
& Conversion Factors Alpha Efficiency 32.76% Beta Efficiency 31.49% dpm/uCI 2.22E+06 Alpha cpm/uCi 7.27E+05 Beta cpm/uCi 6.99E+05 Sampling Information
5   -Sump*
!!:!Ws! 1Hr AR.Qrox. Minytes Flow Rate Total Total Volume Minutes Reactor Location Date Sam21ed Time On Time Off samoled (dm} Row 'ft 3} ml/ft 3 (mil Time Decav fmin.t VBWR First Floor 12/8/2017 16:15 16:35 20 5 100.0 28317 2.83E+06 16:45 17:35 50 40.2 VBWR Basement 12/9/2017 9:23 9:43 20 5 100.0 28317 2.83E+06 I 9:56 10:40 44 46.0 VBWR Fuel Pool 12/9/2017 9:00 9:20 20 5 100.0 28317 2.83E+06 9:30 10:18 48 41.0 EVESR First Floor 12/8/2017 16:40 17:00 20 5 100.0 28317 2.83E+06 17:10 18:00 50 48.4 EVESR Basement 12/9/2017 10:12 10:32 20 5 100.0 28317 2.83E+06 10:47 11:32 45 46.6 EVESR 519' Level 12/9/2017 9:50 10:10 20 5 100.0 28317 2.83E+06 10:30 11:10 40 43.3 GETR First Floor 12/8/2017 17:15 17:35 20 5 100.0 28317 2.83E+06 17:45 18:35 so 35.1 GETR Basement 12/9/2017 7:18 7:38 20 5 100.0 28317 2.83E+06 7:48 8:38 50 45.2 GETR Th1rd Floor 12/9/2017 7:41 8:01 20 5 100.0 28317 2.83E+06 8:21 9:00 39 45.1}}
6 7 Reactor Vessel Head Area                                       !             <I         F                                     <100       <500     <20   <200 100 em~
8 9 Top of Fuel Pool                                               I             *:I       F                                     <100       <500     <20   <:\00   100 em~
10
                                                                                                                                                                              ~
11  Personnel Air Lock                                         . I               ,I         F                                     '100       <500     <20   < 200 100 em~
12 13 Equipment Air Lock                                         <I               <I         F                                     <100       <500       <20   <200 IOOcm 14 15 16 INSTRUMENT USED                       PRM-7     CP-5       R0-20         PNR-4       TBM-         E-120       RM-       RM-           PAC -1SA     LUOLUM-12 SERIAL NUMBER                                               4549                                   1385                                   897 Area Posted: (circle applicable) RA   HRA   CA   RMA     AIRBORNE                         PROBE     u AC-3A (U}         10%   X PROBE     !lr PANCAKE           20%   X OMMEmS
* No entry to basement due to raln water in basement.                         EFF    u 43-4 (U)           10%       EFF (4 p                                     (4 p GEO!                                   GEO.J NEO 289 (REV. 07/10)
 
ATTACHMENT2:           Air Sample Data for Vallecitos Reactor Annual Inspection 2017 Initial                               1 Hour Decay                                   24/48 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       nwm         uCi/ml     ncpm       uCi/ml VBWR     First Floor                                     2.83E+06           1281.30 6.22E*l0       3323.20 1.68E-09     541.10 2.63E-10   1221.80     5.93E-10           2.80 1.36E*12           8.60 4.34E-12 Basement                                       2.83E+06           1562.70 7.59E*10       4024.50 2.03E-09     805.50 3.91E-10   1827.70     8.87E-10         0.60 2.91E-13           5.80 2.93E-12 Fuel Pool                                       2.83E+06           1826.10 8.87E-10       4696.60 2.37E-09     811.70 3.94E-10   1855.40     9.01E-10           1.10 5.34E-13         11.10 S.61E-12 EVESR   First Floor                                     2.83E+06           5906.20 2.87E*09 16961.60 8.57E-09       2885.60 1.40E*09     6429.30 3.12E-09               2.30 1.12E-l2           5.00 2.53E-12 Basement                                       2.83E+06           4734.50 2.30E-09 12859.00 6.50E-09       2424.70 1.18E-09     5572.80 2.71E-09             1.20 5.83E-13         42.70 2.16E-11 519' Level                                     2.83E+06           4021.00 1.95E*09 10887.10 S.SOE-09       2119.60 1.03E..Q9   480.4.20 . 2.33E-09           1.60 7.77E-13           5.70 2.88E-12 GETR     First Floor                                     Z.83E+06           1689.80 8.21E-10       4508.90 2.18E-09     628.80 3.0SE-10   1397.40     6.79E-10         5.30 2.57E-12         15.50 7.83E-12 Basement                                       2.83E+06             1645.90 7.99E*10       4496.20 2.27E-09     764.30 3.71&#xa3;-10   1741.70     8.46&#xa3;-10         1.10 5.34E-13         17.00 8.59E-12 Third Floor                                   2.83E+06 1455.10 7.07E*10       3746.50 1.89&#xa3;-09   798.90 3.88E-10     1859.80     9.03&#xa3;-10
                                                                                                                                                              ~
1.00 4.86E-13-*-
23.70 1.20E-11 Tennelec System "B" Efficiency & Conversion Factors Alpha Efficiency                                            32.76%
Beta Efficiency                                            31.49%
dpm/uCI                                        2.22E+06 Alpha cpm/uCi                                        7.27E+05 Beta cpm/uCi                                        6.99E+05 Sampling Information
                                                                                                                                                                    !!:!Ws!        1Hr                AR.Qrox.
Minytes Flow Rate Total              Total Sam~le Volume        Sam~le        Sam~le    Minutes    Half~Life 3        3 Reactor     Location                         Date Sam21ed Time On                   Time Off samoled         (dm}   Row 'ft } ml/ft             (mil               ~            Time     Decav     fmin.t VBWR       First Floor                             12/8/2017               16:15     16:35         20         5     100.0     28317         2.83E+06             16:45         17:35       50         40.2 VBWR       Basement                                 12/9/2017               9:23       9:43         20         5     100.0     28317         2.83E+06         I   9:56         10:40       44         46.0 VBWR       Fuel Pool                               12/9/2017               9:00       9:20         20         5     100.0     28317         2.83E+06             9:30         10:18       48         41.0 EVESR     First Floor                             12/8/2017               16:40     17:00         20         5     100.0     28317         2.83E+06             17:10         18:00       50         48.4 EVESR     Basement                                 12/9/2017               10:12     10:32         20         5     100.0     28317         2.83E+06             10:47         11:32       45         46.6 EVESR     519' Level                               12/9/2017               9:50     10:10         20         5     100.0     28317         2.83E+06             10:30         11:10       40         43.3 GETR       First Floor                             12/8/2017               17:15     17:35         20         5     100.0     28317         2.83E+06             17:45         18:35     so         35.1 GETR       Basement                                 12/9/2017               7:18       7:38         20         5     100.0     28317         2.83E+06             7:48         8:38       50         45.2 GETR     Th1rd Floor                               12/9/2017               7:41       8:01         20         5     100.0     28317         2.83E+06             8:21         9:00       39         45.1}}

Latest revision as of 21:59, 2 February 2020

GE-Hitachi Nuclear Energy Americas, LLC - Annual Shutdown Reactor Report Supplement for the Year 2017
ML18171A068
Person / Time
Site: Vallecitos Nuclear Center
Issue date: 06/20/2018
From: Feyrer M
GE-Hitachi Nuclear Energy Americas
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
M180129
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  • HITACHI GE Hitachi Nuclear Energy Matt 1. Feyrer Site Manager, vallecitos Nuclear Center 6705 Vallecitos Rd Sunol, CA 94586 USA M180129 T 925 918 6018 Matt.feyrer@ge.com June 20, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001

Subject:

GEH Annual Shutdown Reactor Report Supplement for the Year 2017

References:

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 Control Desk "GEH Annual Shutdown Reactor Reports for the Year 2017, 3/29/18 Enclosed is a supplement to the 2018 Annual Report (Reference 2) for the deactivated Vallecitos Boiling Water Reactor (VBWR}, located at the GE Hitachi, Vallecitos Nuclear Center near Sunol, California.

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

Matt Feyrer, Site Manager Vallecitos Nuclear Center

Enclosure:

VBWR Annual Report No. 53, Supplement dated June 2018 cc: NRC Region IV Administrator J. Parrott, NRC NMSS MJF 18-007

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

ANNUAL REPORT NO. 53 FOR THE YEAR 2017 LICENSE DPR-1 DOCKET 50-18 June 2018

Vallecitos Boiling Water Reactor (Deactivated}

Annual Report No. 53 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWR) in a deactivated status under the authority of Amendment No. 21 to license DPR-1, Docket 50-18, issued Oct 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2.017 to December 31, 2017 is presented, as required by paragraph S.d.2 of the license.

1.0

SUMMARY

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

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

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

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

3.0 RADIATION AND CONTAMINATION Complete radiation and contamination surveys of the fadtity 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.

During the 2017 annual inspection in December a small volume of water was found in the basement of the VBWR containment. Due to this volume of water, no direct surveys or smears were taken in this particular area. In April, another entry was made to re-inspect the area. As water was still present, a sample was taken for analysis wiU1 the results attached below. In Page 1 of3

VBWR Annual Rec:ton No. 53 addition. CR#28719 was initiated to track this issue to resolution. Action items include removing water from the containment basement as well as a formal evaluation of how the water entered into this area. This evaluation is beginning in late June, early July.

Month I Gross beta ~-tCi/ml Gross Alpha ).l.Ci/ml l Tritium ).l.Ci/ml April2018 I 3.46E-07 8.66E-08 l <MDC Page 2 of 3

4.0 ACTIVITIES Routine inspections were conducted during this report period. No other significant activities occurred at VBWR.

S.O ORGANIZATION The organizational structure remained unchanged during 2017. The Site Manager remains M. J.

Feyrer. The VBWR Facility Manager remains M. R. Schrag. The Manager, Regulatory Compliance and EHS, T. M. leik, retired January 2018. J. G. Ayala is currently Acting Manager, Regulatory Compliance and EHS.

6.0 CONCLUSION

GE Hitachi Nuclear Energy concludes that the deactivated VBWR is being maintained in a safe shutdown condition. The inspections, access control, and administratively controlled activities ensure maximum protection for the public health (lnd safety. The procedures will be continued to maintain this high level of protection.

GE Hitachi Nuclear Energy Vallecitos Operations Page 3 of 3

SURVEYOR (print and sign) IREVIEWER NO.

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

D-0105 12/09/17 TIME:

NUCLEAR SAFETY SURVEY RECORD VBWR Containment 0930 liD Routine REASON 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item I> I n TOTAL Distance llr l\7 u u Jly Jlr tt a No. mRild/ll mll.lll mRemlh mRemlil CPM dPM CPM dPM CPM nPM CPM dPM AREA 1 Main Floor - General Area *1 < 1 F <100 <500 <20 <200 IOOcm:

2 - Area Over Reactor Vessel *J *: I F <100 <500 <20 <200 IOOcm*

3 4 Basement - General Area*

5 -Sump*

6 7 Reactor Vessel Head Area  ! <I F <100 <500 <20 <200 100 em~

8 9 Top of Fuel Pool I *:I F <100 <500 <20 <:\00 100 em~

10

~

11 Personnel Air Lock . I ,I F '100 <500 <20 < 200 100 em~

12 13 Equipment Air Lock <I <I F <100 <500 <20 <200 IOOcm 14 15 16 INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM- E-120 RM- RM- PAC -1SA LUOLUM-12 SERIAL NUMBER 4549 1385 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE u AC-3A (U} 10% X PROBE !lr PANCAKE 20% X OMMEmS

  • No entry to basement due to raln water in basement. EFF u 43-4 (U) 10% EFF (4 p (4 p GEO! GEO.J NEO 289 (REV. 07/10)

ATTACHMENT2: Air Sample Data for Vallecitos Reactor Annual Inspection 2017 Initial 1 Hour Decay 24/48 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 nwm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 1281.30 6.22E*l0 3323.20 1.68E-09 541.10 2.63E-10 1221.80 5.93E-10 2.80 1.36E*12 8.60 4.34E-12 Basement 2.83E+06 1562.70 7.59E*10 4024.50 2.03E-09 805.50 3.91E-10 1827.70 8.87E-10 0.60 2.91E-13 5.80 2.93E-12 Fuel Pool 2.83E+06 1826.10 8.87E-10 4696.60 2.37E-09 811.70 3.94E-10 1855.40 9.01E-10 1.10 5.34E-13 11.10 S.61E-12 EVESR First Floor 2.83E+06 5906.20 2.87E*09 16961.60 8.57E-09 2885.60 1.40E*09 6429.30 3.12E-09 2.30 1.12E-l2 5.00 2.53E-12 Basement 2.83E+06 4734.50 2.30E-09 12859.00 6.50E-09 2424.70 1.18E-09 5572.80 2.71E-09 1.20 5.83E-13 42.70 2.16E-11 519' Level 2.83E+06 4021.00 1.95E*09 10887.10 S.SOE-09 2119.60 1.03E..Q9 480.4.20 . 2.33E-09 1.60 7.77E-13 5.70 2.88E-12 GETR First Floor Z.83E+06 1689.80 8.21E-10 4508.90 2.18E-09 628.80 3.0SE-10 1397.40 6.79E-10 5.30 2.57E-12 15.50 7.83E-12 Basement 2.83E+06 1645.90 7.99E*10 4496.20 2.27E-09 764.30 3.71£-10 1741.70 8.46£-10 1.10 5.34E-13 17.00 8.59E-12 Third Floor 2.83E+06 1455.10 7.07E*10 3746.50 1.89£-09 798.90 3.88E-10 1859.80 9.03£-10

~

1.00 4.86E-13-*-

23.70 1.20E-11 Tennelec System "B" Efficiency & Conversion Factors Alpha Efficiency 32.76%

Beta Efficiency 31.49%

dpm/uCI 2.22E+06 Alpha cpm/uCi 7.27E+05 Beta cpm/uCi 6.99E+05 Sampling Information

!!:!Ws! 1Hr AR.Qrox.

Minytes Flow Rate Total Total Sam~le Volume Sam~le Sam~le Minutes Half~Life 3 3 Reactor Location Date Sam21ed Time On Time Off samoled (dm} Row 'ft } ml/ft (mil ~ Time Decav fmin.t VBWR First Floor 12/8/2017 16:15 16:35 20 5 100.0 28317 2.83E+06 16:45 17:35 50 40.2 VBWR Basement 12/9/2017 9:23 9:43 20 5 100.0 28317 2.83E+06 I 9:56 10:40 44 46.0 VBWR Fuel Pool 12/9/2017 9:00 9:20 20 5 100.0 28317 2.83E+06 9:30 10:18 48 41.0 EVESR First Floor 12/8/2017 16:40 17:00 20 5 100.0 28317 2.83E+06 17:10 18:00 50 48.4 EVESR Basement 12/9/2017 10:12 10:32 20 5 100.0 28317 2.83E+06 10:47 11:32 45 46.6 EVESR 519' Level 12/9/2017 9:50 10:10 20 5 100.0 28317 2.83E+06 10:30 11:10 40 43.3 GETR First Floor 12/8/2017 17:15 17:35 20 5 100.0 28317 2.83E+06 17:45 18:35 so 35.1 GETR Basement 12/9/2017 7:18 7:38 20 5 100.0 28317 2.83E+06 7:48 8:38 50 45.2 GETR Th1rd Floor 12/9/2017 7:41 8:01 20 5 100.0 28317 2.83E+06 8:21 9:00 39 45.1