ML20352A287

Amended GEH Annual Shutdown Reactor Reports for the Year 2019

ML20352A287
Person / Time
Site:	Vallecitos, Vallecitos Nuclear Center
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)

Text

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

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 radiological 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 BOILING WATER REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 55 FOR THE YEAR 2019 LICENSE DPR-1 DOCKET 50-18 MARCH 2020 Vallecitos Nuclear Center Sunol, California

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)

I REVIEWER NO.

e HITACHI Name and signatures on Original at GEH Vallecitos D-055 LOCATION DATE:

VALLECITOS NUCLEAR CENTER 06/18/19 NUCLEAR SAFETY SURVEY RECORD VBWR Containment TIME:

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 (cA J (RM~ AIRBORNE PROBE a AC-3A (U) 10%

PROBE

~y PANCAKE 20%

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

EFF.

EFF.

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

GEO.)

NEO 289 (REV. 07/10)

<1 MACHINERY

<1 HATCH

<1 EQUIPMENT HAT C K VBWR MAIN FLOOR

<1 REACTOR PIT

<1 32 CONTACT g 9@30CM

~

( STEAM ~ )

GENERATOR

~

HATCH

~

<1

<1

<1

<1

<1 t/)

=DOSE RATE

=SMEAR LOCATION DOSE RATES IN MRIHR

E_ CONTACT

.a_@ 30CM VBWR BASEMENT AREA REACTOR HEAD

=DOSE RATE

=SMEAR LOCATION DOSE RATES IN MRIHR

Attachment to Survey D-055: VBWR Containment Annual Survey Smear Results Instrument:

Tennelec XLB System A Analyzed By:

Serial No.:

2972-2 Signature:

Calibration Date:

1 Mar 2019 Reviewed:

Beta Efficiency:

33.47%

Beta MDA:

Alpha Efficiency:

36.28%

Alpha MDA:

Sample Date:

6/18/19 Count Date:

Alpha Alpha Level Location (NCPM/100 cm2) (DPM/100 cm2) 1 0

0 2

0 0

3 0

0 4

0 0

5 0

0 Main 6

0 0

Floor 7

0.9 2.5 Levell 8

0 0

9 0

0 10 0.9 2.5 11 0

0 12 0

0 13 0

0 1

0.9 2.5 2

0 0

Rx Head 3

0 0

Level 4 (Bricks) 0 0

5 (Diamond Plate) 0.9 2.5 1

2.9 8.0 2

0 0

3 0

0 4

0 0

Basement 5

0 0

6 2.9 8.0 7 (Sump Cover) 0 0

8 (By Sump) 1.9 5.2 Page 1 of 1 Name and signature on original at GEH Vallecitos Nuclear Center 16.9 dpm 10.5 dpm 6/18/19 Beta Beta (NCPM/100 cm2)

(DPM/100 cm2) 108.2 323 47.2 141 44.2 132 79.2 237 43.2 129 49.2 147 33.2 99.2 37.2 111 24.2 72.3 27.2 81.3 89.2 266 51.2 153 28.2 84.2 95.2 284 28.2 84.2 23.2 69.3 23.2 69.3 104.2 311 1944.2 5810 579.2 1730 701.2 2090 532.2 1590 691.2 2060 738.2 2210 399.2 1190 915.. 2 2730

VBWR & EVESR SITE MAP 8 0 9

10 II 8

\\QQQj I 1 22 TANKO PAD 32 7

0 7

CONCRETE PAD MOCKUP AREA 9

© 9

BUILDING 14 EVESR 18 16 20 30 68 60 118 425 80 180 8

8 8

12 10 12 6

12 BUILDING 90 1000 410

DOSE RATE DOSE RATES IN MICROREM/HR

ATTACHMENT 2:

Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial Sample Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E-10 792.30 3.77E-10 Basement 2.83E+06 820.19 3.60E-10 1991.90 9.47E-10 Fuel Pool 2.83E+06 679.59 2.98E-10 1813.90 8.62E-10 EVESR First Floor 2.83E+06 3227.29 1.42E-09 7953.80 3.78E-09 Basement 2.83E+06 4923.19 2.16E-09 11385.50 5.41E-09 519' Level 2.83E+06 6876.69 3.02E-09 16930.10 8.05E-09 GETR First Floor 2.83E+06 190.09 8.33E-11 548.50 2.61E-10 Basement 2.83E+06 99.59 4.37E-11 245.00 1.16E-10 Third Floor 2.83E+06 124.29 5.45E-11 458.30 2.18E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%

Beta Efficiency dpm/uCi Alpha cpm/uCi Beta cpm/uCi Reactor Location VBWR First Floor VBWR Basement VBWR Fuel Pool EVESR First Floor EVESR Basement EVESR 519' Level GETR First Floor GETR Basement GETR Third Floor 33.47%

2.22E+06 8.05E+05 7.43E+05 Date Sam~led 6/18/2019 6/18/2019 6/25/2019 6/18/2019 6/18/2019 6/18/2019 6/17/2019 6/17/2019 6/25/2019 Sampling Information Flow Minutes Rate Time On Time Off sam~led (cfm) 7:47 8:07 20 5

7:47 8:07 20 5

9:43 10:03 20 5

9:34 9:54 20 5

9:34 9:54 20 5

9:34 9:54 20 5

14:17 14:37 20 5

9:50 10:10 20 5

8:55 9:15 20 5

1 Hour Decay

>24 Hour Decay Alpha Beta Alpha Beta ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml 103.39 4.53E-11 233.50 1.11E-10 0.00 O.OOE+OO 7.00 3.33E-12 260.29 1.14E-10 592.20 2.81E-10 0.49 2.15E-13 21.50 1.02E-11 71.89 3.15E-11 159.20 7.57E-11 1.09 4.78E-13 10.30 4.90E-12 718.89 3.15E-10 1551.40 7.37E-10 0.29 1.27E-13 5.20 2.47E-12 999.79 4.38E-10 2181.90 1.04E-09 2.49 1.09E-12 75.60 3.59E-11 1534.89 6.73E-10 3353.20 1.59E-09 1.09 4.78E-13 59.90 2.85E-11 71.99 3.16E-11 170.30 8.09E-11 1.29 5.66E-13 8.00 3.80E-12 29.29 1.28E-11 76.60 3.64E-11 1.09 4.78E-13 15.00 7.13E-12 43.29 1.90E-11 238.00 1.13E-10 0.79 3.46E-13 43.30 2.06E-11 Initial 1 Hr A~~rox.

Total Total Sam~le Count Count Minutes Half-Life Flow {fe}

ml/fe Volume {ml}

Time Time Decay

{min.}

100.0 28317 2.83E+06 8:54 9:52 58 34.3 100.0 28317 2.83E+06 8:42 9:42 60 36.2 100.0 28317 2.83E+06 10:16 12:10 114 35.2 100.0 28317 2.83E+06 10:39 11:55 76 35.1 100.0 28317 2.83E+06 10:49 12:05 76 33.0 100.0 28317 2.83E+06 10:28 11:44 76 35.1 100.0 28317 2.83E+06 14:45 15:49 64 45.7 100.0 28317 2.83E+06 10:58 12:00 62 35.1 100.0 28317 2.83E+06 9:36 10:36 60 39.4

HITACHI GE Hitachi Nuclear Energy ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 52 FOR THE YEAR 2019 LICENSE DR-10 DOCKET 50-183 MARCH 2020 Vallecitos Nuclear Center Sunol, California

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 Manager Vallecitos Nuclear Center Page 3 of 3 I

SURVEYOR (print and sign)

I REVIEWER NO.

e HITACHI Name and signatures on Original at GEH Vallecitos D-056 LOCATION DATE:

VALLECITOS NUCLEAR CENTER 06/18/19 NUCLEAR SAFETY SURVEY RECORD EVESR Containment TIME:

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 a 43-4 (U) 10%

EFF.

EFF.

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

GEO.)

NEO 289 (REV. 07/10)

ESCAPE HATCH 0

/ ~

~

<1

~ § /

<1

<1 EVESR 549' LEVEL

<1

~

<1 0

<1 EQUIPMENT HATCH

<1

~~

I 0

\\

\\

<1 J

~~

<1 Dose Rates in mRem/hr

<1

<1

<1 EVESR 534' LEVEL

.C0

<1 0

• c******J**

RX

<1 DRAIN

!lillY 7 CONTACT 3@ 30CM

<1 VALVE

<1 l><l 3 CONTACT 1@ 30CM l><l ~A~~~TACT

~ 0 1@ 30CM Dose Rates in mRem/hr

/ff

<1 0 0

<1

\\ I

\\

1 STAIR 1

/

~

<1 EVESR 519' LEVEL

<1 8

0

<1

/

1/

v STAIRS

/

1 RX

<1 Dose Rates in mRem/hr

<1

<1

<1 EVESR 503' LEVEL

<1

<1

<1

<1 0

<1 0

<1

. mRem/hr Dose Rates In

<1 0

EVESR 500' LEVEL IN-CORE FLUX AREA

<1

<1

<1 CJ Dose Rates in mRem/hr

<1

<1

<1

<1 (V

EVESR 487' LEVEL

§

<1

<1

• '---~~~~~~~~~____]:: :::::::::::::: ::

<1

<1

<1

<1

<1

<1

<1

<1

<1 CRD ROOM

(;;'\\ <1 v -

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 cm2)

(DPM/100 cm2)

(NCPM/100 cm2)

(DPM/100 cm2) 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 cm2)

(DPM/100 cm2)

(NCPM/100 cm2)

(DPM/100 cm2) 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 8 0 9

10 II 8

\\QQQj I 1 22 TANKO PAD 32 7

0 7

CONCRETE PAD MOCKUP AREA 9

© 9

BUILDING 14 EVESR 18 16 20 30 68 60 118 425 80 180 8

8 8

12 10 12 6

12 BUILDING 90 1000 410

DOSE RATE DOSE RATES IN MICROREM/HR

ATTACHMENT 2:

Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial Sample Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E-10 792.30 3.77E-10 Basement 2.83E+06 820.19 3.60E-10 1991.90 9.47E-10 Fuel Pool 2.83E+06 679.59 2.98E-10 1813.90 8.62E-10 EVESR First Floor 2.83E+06 3227.29 1.42E-09 7953.80 3.78E-09 Basement 2.83E+06 4923.19 2.16E-09 11385.50 5.41E-09 519' Level 2.83E+06 6876.69 3.02E-09 16930.10 8.05E-09 GETR First Floor 2.83E+06 190.09 8.33E-11 548.50 2.61E-10 Basement 2.83E+06 99.59 4.37E-11 245.00 1.16E-10 Third Floor 2.83E+06 124.29 5.45E-11 458.30 2.18E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%

Beta Efficiency dpm/uCi Alpha cpm/uCi Beta cpm/uCi Reactor Location VBWR First Floor VBWR Basement VBWR Fuel Pool EVESR First Floor EVESR Basement EVESR 519' Level GETR First Floor GETR Basement GETR Third Floor 33.47%

2.22E+06 8.05E+05 7.43E+05 Date Sam~led 6/18/2019 6/18/2019 6/25/2019 6/18/2019 6/18/2019 6/18/2019 6/17/2019 6/17/2019 6/25/2019 Sampling Information Flow Minutes Rate Time On Time Off sam~led (cfm) 7:47 8:07 20 5

7:47 8:07 20 5

9:43 10:03 20 5

9:34 9:54 20 5

9:34 9:54 20 5

9:34 9:54 20 5

14:17 14:37 20 5

9:50 10:10 20 5

8:55 9:15 20 5

1 Hour Decay

>24 Hour Decay Alpha Beta Alpha Beta ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml 103.39 4.53E-11 233.50 1.11E-10 0.00 O.OOE+OO 7.00 3.33E-12 260.29 1.14E-10 592.20 2.81E-10 0.49 2.15E-13 21.50 1.02E-11 71.89 3.15E-11 159.20 7.57E-11 1.09 4.78E-13 10.30 4.90E-12 718.89 3.15E-10 1551.40 7.37E-10 0.29 1.27E-13 5.20 2.47E-12 999.79 4.38E-10 2181.90 1.04E-09 2.49 1.09E-12 75.60 3.59E-11 1534.89 6.73E-10 3353.20 1.59E-09 1.09 4.78E-13 59.90 2.85E-11 71.99 3.16E-11 170.30 8.09E-11 1.29 5.66E-13 8.00 3.80E-12 29.29 1.28E-11 76.60 3.64E-11 1.09 4.78E-13 15.00 7.13E-12 43.29 1.90E-11 238.00 1.13E-10 0.79 3.46E-13 43.30 2.06E-11 Initial 1 Hr A~~rox.

Total Total Sam~le Count Count Minutes Half-Life Flow {fe}

ml/fe Volume {ml}

Time Time Decay

{min.}

100.0 28317 2.83E+06 8:54 9:52 58 34.3 100.0 28317 2.83E+06 8:42 9:42 60 36.2 100.0 28317 2.83E+06 10:16 12:10 114 35.2 100.0 28317 2.83E+06 10:39 11:55 76 35.1 100.0 28317 2.83E+06 10:49 12:05 76 33.0 100.0 28317 2.83E+06 10:28 11:44 76 35.1 100.0 28317 2.83E+06 14:45 15:49 64 45.7 100.0 28317 2.83E+06 10:58 12:00 62 35.1 100.0 28317 2.83E+06 9:36 10:36 60 39.4

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

ANNUAL REPORT NO. 61 FOR THE YEAR 2020 LICENSE TR-1 DOCKET 50-70 MARCH 2020 Vallecitos Nuclear Center Sunol, California

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)

I REVIEWER NO.

e HITACHI Name and signatures on Original at GEH Vallecitos C-020 LOCATION DATE:

VALLECITOS NUCLEAR CENTER 06/17/19 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 1 of 2)

TIME:

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 a 43-4 (U) 10%

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

GEO.)

NEO 289 (REV. 07/10)

SURVEYOR (print and sign)

I REVIEWER NO.

e HITACHI Name and signatures on Original at GEH Vallecitos C-020 LOCATION DATE:

06/17/19 VALLECITOS NUCLEAR CENTER NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of 2)

TIME:

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 a 43-4 (U) 10%

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

GEO.)

NEO 289 (REV. 07/10)

< 1

< 1

< 1 GETR Basement

< 1 CyL.IIIIO£R Sl'oRAG£ A.R£A

< 1

< 1

< 1 f::\\

CRD R~

~ontact

~ '

@30cm 1

o: G* @

~

12o conta *::... *::: :

< 1 3

15 @ 30c

< 1 AUTOCLAVE ELEVATOR

<1 @

< 1

< 1

< 1

< 1 STAIRS

< 1

.1L = Dose Rate

@=Smear Location Rates in mR/hr Dose

< 1

< 1 GETR Level1

< 1

< 1

< 1 @f; 15 contact @

/

6 @ 30cm

< 1

< 1

.JL = Dose Rate

@= Smear Location Rates in mR/hr Dose

Rx

< 1 ELEVATOR

< 1 GETR Level2

< 1 EEHS

< 1

~

~

1~contac

< 1

< 1 7 contact 4@ 30cm

< 1

< 1

< 1 STAIRS

< 1

.JL = Dose Rate

= Smear Location Dose Rates in mR/hr

Rx GETR Level3 Mezzine

< 1

< 1

< 1

< 1

< 1 STAIRS G)

<1

.JL = Dose Rate Gi)= Smear Location Dose Rates in mR/hr

< 1 REACTOR CAVITY

< 1

< 1

< 1 GETR Level4

< 1

< 1

< 1 RAISED PLATFORM AREA

< 1 ELEVATOR

< 1 REACTOR HEAD MISSILE SHIELD

< 1 (iV

< 1

< 1

<1 @

< 1

< 1

< 1

< 1 Drain

• 5 contact 1.5 @ 30c

< 1 t:~\\

OFFICE

< 1 STAIRS G)

< 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 cm2) (DPM/100 cm2) (NCPM/100 cm2) (DPM/100 cm2) 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)

Level 1 0.0 0.0 1,075 3,212 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 cm2) (DPM/100 cm2) (NCPM/100 cm2) (DPM/100 cm2)

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 Level 2 1

0.0 0.0 3

10 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 Mezzanine 1.9 5.2 11 33 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 Top Floor Floor (4)@ Elevator 0.0 0.0 36 108 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 cm2) (DPM/100 cm2) (NCPM/100 cm2) (DPM/100 cm2)

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

~

14 25 47 GETR SITE MAP

~

('*\\(~\\\\ ~"'""'j

\\\\....

35 19 BUILDING 20

~

17 32 50 24 36 60

~

oG 300 a2800

"<~'-""

450 1200 600 I

BUILDING 35 14 20 40 60 30 25 GETR

\\'io

~ 10 o 0 0 17

1. = DOSE RATE DOSE RATES IN MICROREM/HR

ATTACHMENT 2:

Air Sample Data for Vallecitos Reactor Annual Inspection 2019 Initial Sample Alpha Beta Reactor Location Volume (ml) ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 333.99 1.46E-10 792.30 3.77E-10 Basement 2.83E+06 820.19 3.60E-10 1991.90 9.47E-10 Fuel Pool 2.83E+06 679.59 2.98E-10 1813.90 8.62E-10 EVESR First Floor 2.83E+06 3227.29 1.42E-09 7953.80 3.78E-09 Basement 2.83E+06 4923.19 2.16E-09 11385.50 5.41E-09 519' Level 2.83E+06 6876.69 3.02E-09 16930.10 8.05E-09 GETR First Floor 2.83E+06 190.09 8.33E-11 548.50 2.61E-10 Basement 2.83E+06 99.59 4.37E-11 245.00 1.16E-10 Third Floor 2.83E+06 124.29 5.45E-11 458.30 2.18E-10 Tennelec System "A" Efficiency & Conversion Factors Alpha Efficiency 36.28%

Beta Efficiency dpm/uCi Alpha cpm/uCi Beta cpm/uCi Reactor Location VBWR First Floor VBWR Basement VBWR Fuel Pool EVESR First Floor EVESR Basement EVESR 519' Level GETR First Floor GETR Basement GETR Third Floor 33.47%

2.22E+06 8.05E+05 7.43E+05 Date Sam~led 6/18/2019 6/18/2019 6/25/2019 6/18/2019 6/18/2019 6/18/2019 6/17/2019 6/17/2019 6/25/2019 Sampling Information Flow Minutes Rate Time On Time Off sam~led (cfm) 7:47 8:07 20 5

7:47 8:07 20 5

9:43 10:03 20 5

9:34 9:54 20 5

9:34 9:54 20 5

9:34 9:54 20 5

14:17 14:37 20 5

9:50 10:10 20 5

8:55 9:15 20 5

1 Hour Decay

>24 Hour Decay Alpha Beta Alpha Beta ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml 103.39 4.53E-11 233.50 1.11E-10 0.00 O.OOE+OO 7.00 3.33E-12 260.29 1.14E-10 592.20 2.81E-10 0.49 2.15E-13 21.50 1.02E-11 71.89 3.15E-11 159.20 7.57E-11 1.09 4.78E-13 10.30 4.90E-12 718.89 3.15E-10 1551.40 7.37E-10 0.29 1.27E-13 5.20 2.47E-12 999.79 4.38E-10 2181.90 1.04E-09 2.49 1.09E-12 75.60 3.59E-11 1534.89 6.73E-10 3353.20 1.59E-09 1.09 4.78E-13 59.90 2.85E-11 71.99 3.16E-11 170.30 8.09E-11 1.29 5.66E-13 8.00 3.80E-12 29.29 1.28E-11 76.60 3.64E-11 1.09 4.78E-13 15.00 7.13E-12 43.29 1.90E-11 238.00 1.13E-10 0.79 3.46E-13 43.30 2.06E-11 Initial 1 Hr A~~rox.

Total Total Sam~le Count Count Minutes Half-Life Flow {fe}

ml/fe Volume {ml}

Time Time Decay

{min.}

100.0 28317 2.83E+06 8:54 9:52 58 34.3 100.0 28317 2.83E+06 8:42 9:42 60 36.2 100.0 28317 2.83E+06 10:16 12:10 114 35.2 100.0 28317 2.83E+06 10:39 11:55 76 35.1 100.0 28317 2.83E+06 10:49 12:05 76 33.0 100.0 28317 2.83E+06 10:28 11:44 76 35.1 100.0 28317 2.83E+06 14:45 15:49 64 45.7 100.0 28317 2.83E+06 10:58 12:00 62 35.1 100.0 28317 2.83E+06 9:36 10:36 60 39.4