ML24088A176

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GEH - Annual Shutdown Reactor Reports for the Year 2023
ML24088A176
Person / Time
Site: Vallecitos, Vallecitos Nuclear Center  File:GEH Hitachi icon.png
Issue date: 03/28/2024
From: Martinez C
GE-Hitachi Nuclear Energy Americas
To:
Office of Nuclear Material Safety and Safeguards, Document Control Desk
References
M240062
Download: ML24088A176 (1)


Text

HITACHI M240062 March 28, 2024 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001 GE Hitachi Nuclear Energy Carlos Martinez Site Manager, Vallecitos Nuclear Center 6705 Vallecitos Road Sunol, CA 94586 USA T 925-495-9173 Carlosl.Martinez@ge.com

Subject:

GEH Annual Shutdown Reactor Reports for the Year 2023

Reference:

License DPR-1, Docket 50-18 (VBWR), License DR-10, Docket 50-183 (EVESR), License TR-1, Docket 50-70 (GETR)

Enclosed are the 2024 Annual Reports for the deactivated Reactors (Vallecitos Boiling Water Reactor (VBWR), ESADA-Vallecitos Experimental Superheat Reactor (EVESR),

and the General Electric Test Reactor (GETR)} located at the GE Hitachi, Vallecitos Nuclear Center near Sunol, California.

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

Sincerely, Carlos Martinez, Site Manager Vallecitos Nuclear Center

Enclosures:

VBWR Annual Report No. 59 EVESR Annual Report No. 56 GETR Annual Report No. 65 cc: NRC Region IV Administrator J. Parrott, NRC/NMSS/DUWP/RDB CM 24-001

Enclosures VBWR Annual Report No. 59 EVESR Annual Report No. 56 GETR Annual Report No. 65

HITACHI GE Hitachi Nuclear Energy VALLECITOS BOILING WATER REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 59 FOR THE YEAR 2023 LICENSE DPR-1 DOCKET 50-18 MARCH 2024 Val/ecitos Nuclear Center Sunol, California

VBWR Annual Report No. 59 Vallecitos Boiling Water Reactor (Deactivated)

Annual Report No. 59 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, 2023, to December 31, 2023, is presented, as required by paragraph 5.d.2 of the license.

1.0

SUMMARY

All reactor systems have been removed from the containment.

Work was performed on the reactor vessel piping cutting and welding under Change Authorization 2023-01, VBWR Vessel Pipe Cutting and Welding in Preparation for Vessel Removal, approved on April 24, 2023.

Preparation for vessel removal was performed using Change Authorization 2023-02, Mobilize and Prep for VBWR Vessel Removal, approved on September 11, 2023.

Vessel removal was performed using Change Authorization 2023-03, Vessel Removal, approved October 11, 2023.

Concrete core samples of the Bioshield for Part 61 analysis work was performed using Change Authorization 2023-05, Core Drilling Samples from VBWR Bioshield, approved on December 5, 2023.

Structural conditions and 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.

Page 1 of 3

VBWR Annual Report No. 59 3.0 ROUTINE PATROLS The facility was inspected weekly, quarterly, and annually in accordance with written procedures.

Patrols identified the following:

Unchanged efflorescence on the basement walls and floor.

Unchanged spalling of concrete, corrosion stains and rebar corrosion on the Basement Pump Foundation pedestal.

Unchanged Seepage of water into the basement bore location.

These conditions have been evaluated, pose no threat to structural integrity, and are being monitored. The structural condition of the facility is being actively monitored and is structurally sound to ensure maximum protection for public health and safety.

4.0 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.

Analytical results of groundwater samples are available in the Annual Environmental Report submitted on February 15, 2024.

5.0 ACTIVITIES Inspection of the installed gauges showed no propagation of concrete cracking.

There were no preventive or corrective maintenance activities performed having safety significance during the reporting period.

6.0 ORGANIZATION The Site Manager is C. Martinez. The VBWR Facility Manager is J. G. Ayala. The Manager, Regulatory Compliance and EHS remains J. Smyly.

Page 2 of 3

VBWR Annual Report No. 59 7.0 CONCLUSION GE Hitachi Nuclear Energy concludes that the deactivated VBWR is being maintained in a safe shutdown condition. The inspections, access control, and administratively controlled activities ensure maximum protection for the public health and safety. The procedures will be continued to maintain this high level of protection.

GE Hitachi Nuclear Energy Vallecitos Operations t~tA1~

C. Martinez, Manager Vallecitos Nuclear Center Page 3 of 3

I

~,~ URVEYOR

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REVIEWER

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I HITACHI rNO.

D-119 VALLECITOS NUCLEAR CENTER (pnnt)

{sign) l{print)

(si

)

V DATE:

11/14/2023 NUCLEAR SAFETY SURVEY RECORD LOCATION VBWR Containment TIME:

11:00:00 AM

  • Routine REASON D Special VBWR Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT MEASUREMENT LOOSE CONTAMINATION Item p

y n

TOTAL Distance py py (l

(l py py (l

(l AREA (mrad/hr)

(mrem/hr) (mrem/hr)

(mrem/hr)

(cpm)

(dpm)

(cpm)

(dpm)

(cpm)

(dpm)

(cpm)

(dpm) 1 See attached pages 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUMENT USED RadEye SERIAL NUMBER 33168 CAL. DUE DATE 9/16/2024 Area Posted: (mark applicable)

RA 0HRA 0CA 0RMA ARA D Other:

COMMENTS a Probe:

43-93 Efficiency (4n):

10%

See attached survey maps with dose rates, smear locations, and smear results

~ Probe:

43-93 Efficiency (4n):

10%

NSP-3060-F01, NEO 289 (REV. 2/23)

Page of 5

VBWR MAIN FLOOR 0.09 0.05 G

0.044 Survey No.

Date:

D-119 11/14/2023 0.05 0

0 G

Smear Location (100cm2)

Contact Dose Rate in mR/hr All field dose rates in mR/hr

SLANTED WALL 0.3 Survey No.

Date:

D-119 11/14/2023 VBWR BASEMENT AREA 0

SLANTED WALL REACTOR PIT G) 0.16 Q,,]_

SLANTED WALL 0.16 Swtean wit1/2i~ r;t

(~.e.e ~c:\\Cje '5 ')

0.19 0

0

~

Map Legend Smear Location {100cm2)

Contact Dose Rate in mR/hr All field dose rates in mR/hr

HITACHI Counting Lab Analysis Report Issue Date: 12/19/2023 To:-

Sample

Description:

13 Disk Smears from VBWR Containment Sample ID: 23SM564 Instrument:

Tennelec XLB System B Analyzed By:

Serial No.:

2972-1 Beta MDA:

Calibration Date:

2/20/2023 Alpha MDA:

Beta Efficiency:

28.68%

Sample Date:

Alpha Efficiency:

33.91%

Count Date:

Alpha Location NCPM DPM Basement 1 0

<MDA Basement 2 1

<MDA Basement 3 2

<MDA Basement 4 0

<MDA Basement 5 0

<MDA Basement 6 0

<MDA First Floor 7 1

<MDA First Floor 8 1

<MDA First Floor 9 0

<MDA First Floor 10 0

<MDA First Floor 11 0

<MDA First Floor 12 1

<MDA First Floor 13 0

<MDA Signature:_

Attached to Survey 0-119, VBWR Annual Survey.

Page',Kof,-

5

~

t) -\\ l'1 GE Hitachi Vallecitos Nuclear Center Radiological Counting Laboratory 22.6 DPM 8.95 DPM 11/14/2023 11/7/2023 Beta NCPM DPM 22 76 12 41 25 86 35 121 18 62 18 62 21 72 14 48 8

27 20 69 14 48 39 135 19 65

HITACHI Counting Lab Analysis Report Issue Date: 11/3/2023 Sample Date: 11/2/2023 To:-

Sample

Description:

10 Disk Smears from VBWR Vessel Area Sample ID: 23SM502 Instrument:

Tennelec XLB System B Analyzed By:

Serial No.:

29f2-1 Beta MDA:

Calibration Date:

2/20/2023 Alpha MDA:

Beta Efficiency:

28.68%

Sample Date:

Alpha Efficiency:

33.91%

Count Date:

Alpha No.

Location NCPM DPM 1

Drums 1

<MDA 2

Drums 0

<MDA 3

Drums 0

<MDA 4

Drums 0

<MDA 5

Floor 0

<MDA 6

Floor 0

<MDA 7

Floor 0

<MDA 8

Walls 0

<MDA 9

Walls 1

<MDA 10 Walls 1

<MDA Attached to Survey D-119, VBWR Annual Survey Page,4 of 4 5

t; GE Hitachi Vallecitos Nuclear Center Radiological Counting Laboratory 22.6 DPM 8.95 DPM 11/2/2023 11/3/2023 Beta NCPM DPM 9

30 9

30 14 48 13 44 81 281 140 487 64 222 169 588 10 34 32 111

Air Sample Data for VNC Reactor Annual Inspection At Sample Time After Radon Decay After Radon Decay Reactor Location Date Alpha (uCi/ml) Beta (uCi/ml) Alpha (uCi/ml) Beta (uCi/ml)

Alpha (DAC)

Beta (DAC)

Main Floor 11/1/2023 9.91E-10 3.20E-09 0.00E+00 l.44E-12 0.000 0.001 VBWR Basement 11/14/2023 l.69E-09 5.14E-09 4.02E-14 3.96E-12 0.013 0.002 Fuel Pool 11/14/2023 l.13E-09 3.33E-09 4.22E-14 l.83E-12 0.014 0.001 Main Floor 9/28/2023 4.95E-09

1. 76E-08 8.91E-14 5.60E-12 0.030 0.003 EVESR Basement 9/28/2023 l.39E-08 4.62E-08 4.22E-14 6.52E-11 0.014 0.033 519' Level 9/28/2023 8.72E-09 2.97E-08 2.30E-13 2.42E-11 0.077 0.012 Main Floor 9/28/2023 8.26E-10 2.82E-09 4.02E-14 9.SlE-13 0.013 0.000 GETR Basement 10/3/2023 1.49E-09 4.91E-09 0.00E+00 l.23E-12 0.000 0.001 Third Floor 10/3/2023 l.09E-09 3.65E-09 l.17E-13 8.38E-13 0.039 0.000

HITACHI GE Hitachi GE Hitachi Nuclear Energy Nuclear Center ESADA-VALLECITOS EXPERIMENT AL SUPERHEAT REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 56 FOR THE YEAR 2023 LICENSE DR-10 DOCKET 50-183 MARCH 2024 Val/ecitos Nuclear Center Sunol, California Val/ecitos

EVESR Annual Report No. 56 ESADA-Vallecitos Experimental Superheat Reactor (Deactivated)

ANNUAL REPORT NO. 56 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, 2023, to December 31, 2023, is presented, as required by Amendment 7, Appendix A, Technical Specifications, section C. 1.

1.0

SUMMARY

Entry into the containment building was made for routine radiation surveys, quarterly patrols, annual structural inspections, and a general examination of conditions throughout the building.

In accordance with written procedures, the Facility Manager controls access to the containment building.

Structural conditions and 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. The plugs to the reactor vessel, head storage shield, and the wooden cover over the fuel storage pool remain in place.

3.0 ROUTINE PATROLS The facility was inspected weekly, quarterly, and annually in accordance with written procedures.

The structural condition of the facility remains actively monitored, stable and structurally sound to ensure maximum protection for public health and safety.

4.0 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.

Analytical results of groundwater samples are available in the Annual Environmental Report submitted on February 15, 2024.

Page 1 of 2

EVESR Annual Report No. 56 5.0 ACTIVITIES Routine patrols and inspections were conducted during this report period.

There were no preventive or corrective maintenance activities performed having safety significance during the reporting period.

6.0 ORGANIZATION The Site Manager is C. Martinez. The EVESR Facility Manager is J. G. Ayala. The Manager, Regulatory Compliance and EHS remains J. Smyly.

7.0 CONCLUSION GE Hitachi Nuclear Energy concludes that the deactivated ESADA-Vallecitos Experimental Superheat Reactor is being maintained in a safe shutdown condition. The inspections, access control, and administratively controlled activities ensure maximum protection for the public health and safety. The procedures will be continued to maintain this high level of protection.

GE Hitachi Nuclear Energy Vallecitos Operations t~tA1~

C. Martinez, Manager Vallecitos Nuclear Center Page 2 of 2

HITACHI

!~

NO.

D-091 VALLECITOS NUCLEAR CENTER DATE:

9/28/2023 I

NUCLEAR SAFETY SURVEY RECORD LOCATION EVESR TIME:

10:30 X

Routine REASON D

Special Annual ITEMS OR LOCATION DOSE RATE DIRECT MEASUREMENT LOOSE CONTAMINATION Item

~

y 11 TOTAL

~y h

a a

~ y

~y a

a AREA (mrad/hr)

(mrem/hr) (mrem/hr)

(mrem/hr)

Distance (cpm)

(dpm)

(cpm)

(dpm)

(cpm)

(dpm)

(cpm)

(dpm) 1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 INSTRUMENT USED Radeye SERIAL NUMBER 34372 CAL. DUE DATE 6/10/2024 Area Posted: (mark applicable)

RA 0HRA 0CA 0RMA ARA 0

Other:

COMMENTS a Probe:

Efficiency (4n):

10%

See attached maps and smear results.

13 Probe:

Efficiency (4n):

10%

NSP-3060-F01, NEO 289A (REV. 2/23)

Page of

~

ESCAPE HATCH 2

0.014 0

I

/

Survey No.

EVESR 549' LEVEL 0

0.062 0

0.023

\\

0

)

0.018 5

0 0.030

(

\\

0

\\

0.016


)

G 0.011 0

Map Legend Smear Location Q Contact Dose Rate in mR/hr All field dose rates in mR/hr

EVESR 534 1 LEVEL 0.112 0

0 DRAIN 0

0.111 0.030 txJ VALVE 0.200

~

txJ LVE J.

0.200 0

Survey No.

Date:

0 Map Legend Smear Location D-091 09/28/23 Q Contact Dose Rate in mR/hr All field dose rates in mR/hr

EVESR 519 1 LEVEL 0

0 8 0

0.021 0

Survey No.

Date:

Map Legend Q Smear Location 0-091 09/28/23 Q Contact Dose Rate in mR/hr All field dose rates in mR/hr

0.015 0

0 0

Survey No.

Date:

D-091 09/28/23 EVESR 503 1 LEVEL 0

0.019 0

STAIRS1,---1 0.010 0

0.023 0.035

D 0

1:

0 0

  • oo"' 00°0 0* **

Map Legend Q Smear Location Q Contact Dose Rate in mR/hr All field dose rates in mR/hr 7

EVESR 500' LEVEL IN-CORE FLUX AREA Survey No.

D-091 Date:

09/28/23 0

0 Map Legend Q Smear Location Q Contact Dose Rate in mR/hr All field dose rates in mR/hr

EVESR 487 1 LEVEL 0

0.045 0.017 Survey No.

Date:

D-091 09/28/23 0.033 CAD ROOM 0

Map Legend Q Smear Location Q Contact Dose Rate in mR/hr All field dose rates in mR/hr

HITACHI GE Hitachi Vallecitos Nuclear Center Radiological Counting Laboratory EVESR Containment Smear Results - 2023 Annual Survey Instrument:

Tennelec XLB System B Analyzed By:

Serial No. :

2972-1 Signature:

Calibration Date:

2/20/2023 Reviewed:

Beta Efficiency:

28.68%

Beta MDA:

"'22.6 DPM / 100 cm 2 Alpha Efficiency:

33.91%

Alpha MDA:

8.95 DPM / 100 cm2 Sample Date:

9/28/2023 Count Date:

10/3/2023 Alpha Beta No.

Location NCPM/100 cm2 DPM/100cm2 NCPM/100 cm2 DPM/100 cm2 1

549' Level 0

<MDA 18.7 65.2 2

549' Level 0

<MDA 17.7 61.7 3

549' Level 0.99

<MDA 59.7 208.2 4

549' Level 0

<MDA 42.7 148.9 5

549' Level 0

<MDA 90.7 316.2 6

549' Level 1.99

<MDA 30.7 107.0 7

549' Level 0

<MDA 11.7 40.8 8

549' Level 0

<MDA 19.7 68.7 9

549' Level 0.99

<MDA 26.7 93.1 10 549' Level 0

<MDA 38.7 134.9 11 549' Level 0

<MDA 12.7 44.3 12 549' Level 2.99

<MDA 46.7 162.8 13 534' Level 0.99

<MDA 66.7 232.6 14 534' Level 0.99

<MDA 1233.7 4301.6 15 534' Level 0

<MDA 174.7 609.1 16 534' Level 0

<MDA 129.7 452.2 17 534' Level 0

<MDA 157.7 549.9 18 534' Level 0

<MDA 126.7 441.8 19 534' Level 0

<MDA 1274.7 4444.6 20 534' Level 0

<MDA 116.7 406.9 21 519' Level 1.99

<MDA 78.7 274.4 22 519' Level 0

<MDA 100.7 351.1 23 519' Level 0

<MDA 72.7 253.5 24 519' Level 0

<MDA 167.7 584.7 25 519' Level 0

<MDA 54.7 190.7 26 519' Level 0

<MDA 54.7 190.7

HITACHI Alpha No.

Location NCPM/100 cm2 DPM/100cm2 27 503' Level 0

<MDA 28 503' Level 0.99

<MDA 29 503' Level 0.99

<MDA 30 503' Level 1.99

<MDA 31 503' Level 0

<MDA 32 503' Level 0

<MDA 33 503' Level 1.99

<MDA 34 503' Level 1.99

<MDA 35 503' Level 0.99

<MDA 36 503' Level 0.99

<MDA 37 500' Level 0.99

<MDA 38 503' Level 0

<MDA 39 503' Level 0.99

<MDA 40 487' Level 0.99

<MDA 41 487' Level 0

<MDA 42 487' Level 0

<MDA 43 487' Level 0

<MDA 44 487' Level 0.99

<MDA 45 487' Level 0.99

<MDA GE Hitachi Vallecitos Nuclear Center Radiological Counting Laboratory Beta NCPM/100 cm2 DPM/100 cm2 313.7 1093.8 507.7 1770.2 405.7 1414.6 156.7 546.4 1420.7 4953.6 197.7 689.3 357.7 1247.2 347.7 1212.3 340.7 1187.9 945.7 3297.4 585.7 2042.2 400.7 1397.1 521.7 1819.0 105.7 368.S 162.7 567.3 71.7 250.0 67.7 236.1 39.7 138.4 80.7 281.4

Air Sample Data for VNC Reactor Annual Inspection At Sample Time After Radon Decay After Radon Decay Reactor Location Date Alpha (uCi/ml) Beta (uCi/ml) Alpha (uCi/ml) Beta (uCi/ml)

Alpha (DAC)

Beta (DAC)

Main Floor 11/1/2023 9.91E-10 3.20E-09 0.00E+00 l.44E-12 0.000 0.001 VBWR Basement 11/14/2023 l.69E-09 5.14E-09 4.02E-14 3.96E-12 0.013 0.002 Fuel Pool 11/14/2023 l.13E-09 3.33E-09 4.22E-14 l.83E-12 0.014 0.001 Main Floor 9/28/2023 4.95E-09

1. 76E-08 8.91E-14 5.60E-12 0.030 0.003 EVESR Basement 9/28/2023 l.39E-08 4.62E-08 4.22E-14 6.52E-11 0.014 0.033 519' Level 9/28/2023 8.72E-09 2.97E-08 2.30E-13 2.42E-11 0.077 0.012 Main Floor 9/28/2023 8.26E-10 2.82E-09 4.02E-14 9.SlE-13 0.013 0.000 GETR Basement 10/3/2023 1.49E-09 4.91E-09 0.00E+00 l.23E-12 0.000 0.001 Third Floor 10/3/2023 l.09E-09 3.65E-09 l.17E-13 8.38E-13 0.039 0.000

HITACHI GE Hitachi Nuclear Energy GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 65 FOR THE YEAR 2023 LICENSE TR-1 DOCKET 50-70 MARCH 2024 Val/ecitos Nuclear Center Sunol, California

GETR Annual Report No. 65 General Electric Test Reactor (Deactivated)

ANNUAL REPORT NO. 65 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, 2023 to December 31, 2023 is presented.

1.0

SUMMARY

The facility remains in predominately the same condition described in Annual Report No. 64. Entry into the reactor building was made for routine radiation surveys and a general examination of conditions throughout the building. The crane, and ventilation were serviced and tested in 2023 in anticipation of beginning remediation activities.

Such activities have not begun.

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

2.0 STATUS OF FACILITY In accordance with written procedures, the Facility Manager controls access to the containment building and general systems. The facility continues to be in deactivated status. There were no changes authorized by the Facility Manager pursuant to 10CFR50.59{a) in 2023.

3.0 ROUTINE PATROLS The facility was inspected weekly, quarterly, and annually in accordance with written procedures.

The presence of minimal efflorescence was identified on facility basement walls during the annual inspection. This condition was evaluated and determined to not pose a structural issue.

The structural condition of the facility remains actively monitored, stable and structurally sound to ensure maximum protection for public health and safety.

4.0 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 Page 1 of 2

GETR Annual Report No. 65 presented in attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.

4.1 GETR Stack Although maintenance was performed on the stack in 2023, 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.

Analytical results of groundwater samples can be found in the Annual Environmental Report submitted on February 15, 2024.

5.0 ACTIVITIES Inspection of the installed gauges showed no propagation of concrete cracking.

There were no preventive or corrective maintenance activities performed having safety significance during the reporting period.

6.0 ORGANIZATION The Site Manager is C. Martinez. The GETR Facility Manager is J.G. Ayala. The Manager, Regulatory Compliance and EHS remains J. Smyly.

7.0 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 f~1~

C. Martinez, Manager Vallecitos Nuclear Center Page 2 of 2

SURVEYOR I REVIEWER

~

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HITACHI I

NO.

C-028 VALLECITOS NUCLEAR CENTER (print)

/(srgn) lPrm11

\\ l"'Y"I _.

, DATE:

I 0/3/2023 NUCLEAR SAFETY SURVEY RECORD LOCATION GETR TIME:

1000

!El Routine REASON Annual Survey Special ITEMS OR LOCATION DOSE RATE DIRECT MEASUREMENT LOOSE CONTAMINATION Item p

y n

TOTAL Distance py py a

a py py a

a AREA (mrad/hr)

(mrem/hr)

(mrem/hr)

(mrem/hr)

(cpm)

(dpm)

(cpm)

(dpm)

(cpm)

(dpm)

(cpm)

(dpm) 1

$tt ~.\\\\a°"tJ p~e,':>

l-\\9v I

V 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUMENT USED RadEye RadEye SERIAL NUMBER 34372 34345 CAL. DUE DATE 6/10/2024 9/16/2024 Area Posted: (circle applicable) (RA) HRA ( CA)~ ARA a Probe: N/A

~ Probe: N/A COMMENTS Smear results are located on the attached lab report.

Efficiency (4n):

10%

Efficiency ( 4n):

10%

NSP-3060-F02, NEO 289A (REV. 12/22)

?~(. \\ ck 9

0 Survey No.

Date:

C-028 10/3/23 GETR 3RD FLOOR 0

0 0.123 ORAi fr0

.5 0

0 REACTOR CAVITY 17;\\FUEL qRIDGE 0.050 0

STAIRS 0.046 0.315 0.080 0 0.020 0

0.018 RAISED PLATFORM AREA 0

STEP OFF PAO HIGH CONTAMINATION AREA BOUNDARY GENERAL AREA DOSE RATE O*

O*

CONTACT DOSE RATE SMEAR LOCATION (100cm')

GETR 2ND FLOOR O.DlS 0

EEHS 0

0 0.028 0.020 0

0 0.027 0

0.225 Survey No.

Date:

Page Z of }'

~

"I 0

C-028 10/3/23 MANWAY 0.011 G)

G)

~ STEP OFF PAD HCA HIGH CONTAMINATION AREA BOUNDARY o*

O

  • GENERAL AREA DOSE RA TE CONTACT DOSE RATE SMEAR LOCATION (100cm')

GETR MEZZANINE (OPEN AREA) 0.011 0

0.021 0

0.020 0

STAIRS 0.013 0 Survey No.

Date:

Page p ot )5

'-\\

q STEP OFF PAD C-028 10/3/23 HCA HIGH CONTAMINATION AREA BOUNDARY GENERAL AREA DOSE RATE 0

  • CONTACT DOSE RATE 0
  • SMEAR LOCATION (100cm2)

0 GETR 1 ST FLOOR 0

0.730 0

0 0.070 0 STAIRS 0.027 0

0.021 EQUIPMENT HATCH 7

Survey No.

0 0.207 HCA O*

0*

C-028 10/3/23 0.255 0

0.111 STEP OFF PAD HIGH CONTAMINATION AREA BOUNDARY GENERAL AREA DOSE RATE CONTACT DOSE RATE SMEAR LOCATION (1 00cm')

0.460 0

GETR BASEMENT 0

0.050 ~

~

0 0

0 0.050 0.047 Survey No.

Date:

Page $ ot)5

'I C-028 10/3/23 CYLINDER STORAGE AREA 0.043 0

STEP OFF PAD HCA HIGH CONTAMINATION AREA BOUNDARY 0

0 GENERAL AREA DOSE RATE CONTACT DOSE RATE SMEAR LOCATION (100cm2)

HITACHI GE Hitachi Vallecitos Nuclear Center Radiological Counting Laboratory GETR Containment Annual Survey Disk Smear Results - 2023 Instrument:

Tennelec XLB System B Analyzed By:

Serial No.:

2972-1 Signature:

Ca libration Date:

2/20/2023 Reviewed:

Beta Efficiency:

28.68%

Beta MDA:

22.6 DPM / 100 cm 2 Alpha Efficiency:

33.91%

Alpha MDA:

8.95 DPM / 100 cm 2 Sample Date:

10/3/2023 Count Date:

10/10/2023 Alpha Beta No.

Location NCPM/100 cm2 DPM/100cm2 NCPM/100 cm2 DPM/100 cm 2 1

Basement #1 1

<MDA 35 121 2

Basement #2 0

<MDA 367 1279 3

Basement #3 0

<MDA 48 166 4

Basement #4 0

<MDA 93 323 5

Basement #5 0

<M DA 54 187 6

Basement #6 1

<MDA 54 187 7

Basement #7 1

<MDA 61 212 8

Basement #8 1

<MDA 83 288 9

Basement #9 0

<MDA 64 222 10 Basement #10 0

<MDA 250 871 11 Basement #11 0

<MDA 135 470 12 Basement #12 0

<MDA 95 330 13 Basement #13 0

<MDA 116 403 14 Basement #14 0

<MDA 94 327 15 Basement #15 0

<MDA 253 881 16 Basement #16 1

<MDA 1086 3786 17 Basement #17 0

<MDA 285 993 18 Basement #18 1

<MDA 1231 4291 19 First Floor #1 0

<MDA 13 44 20 First Floor #2 0

<MDA 2

<MDA 21 First Floor #3 0

<MDA 7

23 22 First Floor #4 0

<MDA 16 55 23 First Floor #5 0

<MDA 22 76 24 First Floor #6 0

<MDA 10 34 25 First Floor #7 0

<MDA 2

<MDA 26 First Floor #8 0

<MDA 16 55 Page): of)'

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HITACHI No.

Location 27 First Floor #9 28 First Floor #10 29 First Floor #11 30 First Floor #12 First Floor #13 First Floor #14 First Floor #15 First Floor #16 31 Second Floor #1 32 Second Floor #2 33 Second Floor #3 34 Second Floor #4 35 Second Floor #5 36 Second Floor #6 37 Second Floor #7 38 Second Floor #8 39 Second Floor #9 40 Second Floor #10 41 Second Floor #11 42 Second Floor #12 43 Mezzanine #1 44 Mezzanine #2 45 Mezzanine #3 46 Mezzanine #4 47 Mezzanine #5 48 Mezzanine #6 49 Third Floor #1 so Third Floor #2 51 Third Floor #3 52 Third Floor #4 53 Third Floor #5 54 Third Floor #6 55 Third Floor #7 56 Third Floor #8 57 Third Floor #9 58 Third Floor #10 59 Third Floor #11 Alpha NCPM/100 cm2 DPM/100 cm2 0

0 0

0 0

0 0

1 0

0 0

0 0

0 0

0 1

1 0

0 0

0 1

0 0

1 1

0 1

1 0

0 1

1 2

1 0

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

<MDA

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6 1

<MDA

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<MDA GE Hitachi Vallecitos Nuclear Center Radiological Counting Laboratory Beta NCPM/100 cm2 DPM/100 cm2 14 48 56 194 41 142 55 191 89 309 30 104 41 142 60 208 19 65 15 51 4

<MDA 28 97 46 159 12 41 25 86 11 37 71 247 3

<MDA 20 69 8

27 17 58 32 111 16 55 17 58 9

30 107 372 70 243 31 107 447 1558 136 473 117 407 113 393 181 630 325 1132 674 2349 378 1317 460 1603

HITACHI No.

Location 60 Third Floor #12 61 Third Floor #13 62 Third Floor #14 63 Third Floor #15 64 Third Floor #16 65 Third Floor #17 66 Third Floor #18 67 Third Floor #19 Alpha NCPM/100 cm2 DPM/100 cm 2 0

0 2

0 1

0 0

0

<MDA

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<MDA

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<MDA

<MDA

<MDA Page 3 of i

" 4 GE Hitachi Vallecitos Nuclear Center Radiological Counting Laboratory Beta NCPM/100 cm2 DPM/100 cm2 18 62 78 271 24 83 814 2837 1607 5602 60 208 376 1310 236 822

Air Sample Data for VNC Reactor Annual Inspection At Sample Time After Radon Decay After Radon Decay Reactor Location Date Alpha (uCi/ml) Beta (uCi/ml) Alpha (uCi/ml) Beta (uCi/ml)

Alpha (DAC)

Beta (DAC)

Main Floor 11/1/2023 9.91E-10 3.20E-09 0.00E+00 l.44E-12 0.000 0.001 VBWR Basement 11/14/2023 l.69E-09 5.14E-09 4.02E-14 3.96E-12 0.013 0.002 Fuel Pool 11/14/2023 l.13E-09 3.33E-09 4.22E-14 l.83E-12 0.014 0.001 Main Floor 9/28/2023 4.95E-09

1. 76E-08 8.91E-14 5.60E-12 0.030 0.003 EVESR Basement 9/28/2023 l.39E-08 4.62E-08 4.22E-14 6.52E-11 0.014 0.033 519' Level 9/28/2023 8.72E-09 2.97E-08 2.30E-13 2.42E-11 0.077 0.012 Main Floor 9/28/2023 8.26E-10 2.82E-09 4.02E-14 9.SlE-13 0.013 0.000 GETR Basement 10/3/2023 1.49E-09 4.91E-09 0.00E+00 l.23E-12 0.000 0.001 Third Floor 10/3/2023 l.09E-09 3.65E-09 l.17E-13 8.38E-13 0.039 0.000