ML16082A451

GE-Hitachi Nuclear Energy - Annual Shutdown Reactor Reports for 2015

ML16082A451
Person / Time
Site:	Vallecitos Nuclear Center, Vallecitos
Issue date:	03/22/2016
From:	Caine T GE-Hitachi Nuclear Energy Americas
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML16082A449	List: ML16082A450 ML16082A451
References
TAC 16-004
Download: ML16082A451 (17)

Text

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

ANNUAL REPORT NO. 51 FOR THE VEAR 2015 LICENSE DPR-1 DOCKET 50-18 MARCH 2016

VBWR Annual Report No. 51 Vallecitos Boiling Water Reactor (Deactivated)

I

• Annual Report No. 51 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor IVBWR) in a deactivated status under the authority of Amendment No. 21 to License DPR-1, Docket 1 lo r ..11 o

50-18, issued Oct 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2015 to December 31, 2015 is presented, as required by paragraph 5.d.2 of the license.

1.0

SUMMARY

,r 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.

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

Page 1 af 2

VBWR Annual Report No. 51 5.0 ORGANIZATION The organizational structure remained unchanged during 2015. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager. Regulatory Compliance and EHS remains T. M. Leik.

6.0 CONCLUSION

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

GE Hitachi Nuclear Energy Vallecitos Operations T.A. Caine Manager Vallecitos Nuclear Center f!Ogt2of2

Attachment 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signature on original at GEH Vallecitos D-054 8 HITACHI LOCATION DATE:

11/14/15 VALLECITOS NUCLEAR CENTER TIME:

NUCLEAR SAFETY SURVEY RECORD VBWR Containment 0800 REASON 1:&1 Routine 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item ll 1 n TOTAL Distance llr jly a a jly Jly a a No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 2

1 Main Floor- General Area <0.5 <0.5 F <100 <500 <20 <200 100 em 2

2 - Area Over Reactor Vessel <0.5 <0.5 F <100 <500 <20 <200 100 cm 3

2 4 Basement- General Area <1 <1 F <100 <500 <20 <200 100 cm 5 -Sump 2 5 7 c 150 750 <20 <200 100 cm 2

6 2

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

2 9 Top of Fuel Pool <0.5 <0.5 F <100 <500 <20 <200 100 cm 10 l

11 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOcm 12 2

13 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 cm 14 15 16 INSTRUMENT USED PRM -7 CP - 5 R0 - 20 PNR-4 TBM- E -120 RM- RM- PAC-1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: {circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC- 3A {U) 10% X PROBE py PANCAKE 20% X COMMENTS EFF . a 43-4 {U) 10% EFF.

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

NEO 289 {REV. 0711 0)

AITACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2015 Initial 1 Hour Decay 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 ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 2210.45 1.02E-09 5887.16 2.73E-09 978.99 4.50E-10 352.75 1.62E-10 0.27 1.24E-13 179.69 8.33E-11 Basement 2.83E+06 2039.96 9.38E-10 5281.56 2.45E-09 639.56 2.94E-10 1373.31 6.32E-10 0.70 3.22E-13 21.14 9.80E-12 Fuel Pool 2.83E+06 2067.26 9.51E-10 5297.21 2.46E-09 1096.67 5.04E-10 2440.18 1.12E-09 0.90 4.14E-13 9.42 4.37E-12 EVESR First Floor 2.83E+06 5163.65 2.38E-09 14342.86 6.65E-09 3180.74 1.46E-09 7079.93 3.26E-09 0.60 2.76E-13 1.15 5.33E-13 Basement 2.83E+06 6219.82 2.86E-09 16754.30 7.77E-09 2553.03 1.17E-09 5429.47 2.50E-09 0.40 1.84E-13 14.87 6.89E-12 519' Level 2.83E+06 6213.91 2.86E-09 16797.99 7.79E-09 3347.47 1.54E-09 7481.06 3.44E-09 0.80 3.68E-13 4.33 2.01E-12 GETR First Floor 2.83E+06 971.07 4.47E-10 2391.69 1.11E-09 452.53 2.08E-10 965.12 4.44E-10 0.20 9.20E-14 5.40 2.50E-12 Basement 2.83E+06 937.69 4.31E-10 2319.45 1.08E-09 464.01 2.13E-10 1041.09 4.79E-10 0.30 1.38E-13 3.19 1.48E-12 Third Floor 2.83E+06 808.45 3.72E-10 1955.49 9.06E-10 65.78 3.03E-11 131.32 6.04E-11 0.50 2.30E-13 14.26 6.61E-12 Tennelec System "A" Efficiency & Conversion Factors

• Note: Lack of P10 gas prevented 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> count.

Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Sampling Information Flow Minutes Rate Total Total Sam~le 3 3 Reactor Location Date Sam~led Time On Time Off sam~led (cfm) Flow (ft } ml/ft Volume (ml}

VBWR First Floor 11/14/2015 7:00 7:20 20 5 100.0 28317 2.83E+06 VBWR Basement 11/14/2015 7:40 8:00 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/14/2015 7:20 7:40 20 5 100.0 28317 2.83E+06 EVESR First Floor 11/14/2015 8:35 8:55 20 5 100.0 28317 2.83E+06 EVESR Basement 11/14/2015 9:25 9:45 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/14/2015 9:00 9:20 20 5 100.0 28317 2.83E+06 GETR First Floor 11/14/2015 11:35 11:55 20 5 100.0 28317 2.83E+06 GETR Basement 11/14/2015 12:00 12:20 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/14/2015 12:25 12:45 20 5 100.0 28317 2.83E+06

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

ANNUAL REPORT NO. 48 FOR THE VEAR 2015 LICENSE DR-10 DOCKET 50-183 MARCH 2016

EVESR Annual Report No. 48 ESADA-Vallecitos Experimental Superheat Reactor (Deactivated)

ANNUAL REPORT NO. 48 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, 2015 to December 31, 2015 is presented, as required by Amendment 7, Appendix A. Technical Specifications, section C. 1.

1.0 SUMMARV 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.

4.0 ACTIVIT! ES Routine inspections were conducted during this report period.

The equipment disposal concluded during 2010.

Page 1 of 2

EVESR Annual Report No. 48 5.0 ORGANIZATION The organizational structure remained unchanged during 2015. The S1te Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager.

Regulatory Compliance and EHS remains T. M. Leik.

6.0 CONCLU~ION GE Hitachi Nuclear Energy concludes that the deactivated ESADA-Vollecitos Experimental Superheat Reactor is being maintained in o safe shutdown condition.

The inspections, access control, and administratively controlled activities ensure maximum protection for the public health and safety. The procedures will be continued to maintain this high level of protection.

GE Hitachi Nuclear Energy Vallecitos Operations T.A.Caine Manager Vallecitos Nuclear Center

Attachment 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signature on original at GEH Vallecitos D-055 HITACHI LOCATION DATE:

VALLECITOS NUCLEAR CENTER 11/14/15 TIME:

NUCLEAR SAFETY SURVEY RECORD EVESR Containment 0900 REASON 1:&1 Routine 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item p y n TOTAL Distance py py a a py py a a No. mRad/h mRih mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 2

1 Top of Spent Fuel Pool (Main Floor) <0.5 <0.5 F <100 <500 <20 <200 100 em 2

2 3 487' Level (Basement) <I <I F 200 1000 <20 <200 100 cm 2

4 503' Level <0.5 <0.5 F <100 <500 <20 <200 100 em 5 519' Level <0.5 <0.5 c 100 500 <20 <200 100 cm 2

6 534' Level - General Area <1-1.5 <1-1.5 c 500 2500 <20 <200 100 cm 2

7 - Floor Drain 7 7 F 8 - Emergency Cooling Valves 1-4 1-4 c 2

9 549' Level <0.5 <0.5 F 100 500 <20 <200 100 cm 10 2

11 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 cm 2

12 Personnel Air Lock <0.5 <0.5 F 100 500 <20 <200 IOOcm 13 14 15 16 INSTRUMENT USED PRM

• 7 CP - 5 R0-20 PNR-4 TBM- E -120 RM- RM- PAC -1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC- 3A (U) 10% X PROBE J3y PANCAKE 20% X OMMENTS EFF. a 43-4 (U) 10% EFF .

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

NEO 289 (REV. 0711 0)

ATIACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2015 Initial 1 Hour Decay 48 Hour Decay

• Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (mil ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 2210.45 1.02E-09 5887.16 2.73E-09 978.99 4.50E-10 352.75 1.62E-10 0.27 1.24E-13 179.69 8.33E-11 Basement 2.83E+06 2039.96 9.38E-10 5281.56 2.45E-09 639.56 2.94E-10 1373.31 6.32E-10 0.70 3.22E-13 21.14 9.80E-12 Fuel Pool 2.83E+06 2067.26 9.51E-10 5297.21 2.46E-09 1096.67 5.04E-10 2440.18 1.12E-09 0.90 4.14E-13 9.42 4.37E-12 EVESR First Floor 2.83E+06 5163.65 2.38E-09 14342.86 6.65E-09 3180.74 1.46E-09 7079.93 3.26E-09 0.60 2.76E-13 1.15 5.33E-13 Basement 2.83E+06 6219.82 2.86E-09 16754.30 7.77E-09 2553.03 1.17E-09 5429.47 2.50E-09 0.40 1.84E-13 14.87 6.89E-12 519' Level 2.83E+06 6213.91 2.86E-09 16797.99 7.79E-09 3347.47 1.54E-09 7481.06 3.44E-09 0.80 3.68E-13 4.33 2.01E-12 GETR First Floor 2.83E+06 971.07 4.47E-10 2391.69 1.11E-09 452.53 2.08E-10 965.12 4.44E-10 0.20 9.20E-14 5.40 2.50E-12 Basement 2.83E+06 937.69 4.31E-10 2319.45 1.08E-09 464.01 2.13E-10 1041.09 4.79E-10 0.30 1.38E-13 3.19 1.48E-12 Third Floor 2.83E+06 808.45 3.72E-10 1955.49 9.06E-10 65.78 3.03E-11 131.32 6.04E-11 0.50 2.30E-13 14.26 6.61E-12 Tennelec System "A" Efficiency & Conversion Factors

• Note: Lack of P10 gas prevented 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> count.

Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Sampling Information Flow Minutes Rate Total Total Sam~le 3 3 Reactor Location Date Sam~led Time On Time Off sam~led (cfm) Flow (ft } ml/ft Volume (ml}

VBWR First Floor 11/14/2015 7:00 7:20 20 5 100.0 28317 2.83E+06 VBWR Basement 11/14/2015 7:40 8:00 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/14/2015 7:20 7:40 20 5 100.0 28317 2.83E+06 EVESR First Floor 11/14/2015 8:35 8:55 20 5 100.0 28317 2.83E+06 EVESR Basement 11/14/2015 9:25 9:45 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/14/2015 9:00 9:20 20 5 100.0 28317 2.83E+06 GETR First Floor 11/14/2015 11:35 11:55 20 5 100.0 28317 2.83E+06 GETR Basement 11/14/2015 12:00 12:20 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/14/2015 12:25 12:45 20 5 100.0 28317 2.83E+06

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

ANNUAL REPORT NO. 57 FOR THE YEAR 2015 LICENSE TR-1 DOCKET 50-70 MARCH 2016

GETR Annual Report No. 57 General Electric Test Reactor (Deactivated)

ANNUAL REPORT NO. 57 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. In this annual report, a summary of the status of the facility for the period of January 1, 2015 to December 31, 2015 is presented.

1.0

SUMMARY

The facility remains in essentially the same condition described in Annual Report No. 54. Entry into the reactor building was made for routine radiation surveys and a general examination of conditions throughout the building. The crane, elevator, and ventilation were serviced and tested in 2011 in anticipation of beginning remediation activities. Such activities have not begun.

Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review. There were no releases from the stack.

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 2015.

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.

The data below are from sample and dosimeter results accumulated during 2015.

These data are for the entire VNC site and include the effects of operations other than GETR.

Page 1 of 3

GETR Annual Report No. 57 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 not yet fully operational, and the stack air flow has not been calibrated. Thus no concentration data is available for 2015.

3.2 Air Monitors (Yearly average of all meteorological stations.!

Four environmental air-monitoring stations are positioned approximately 90 degrees apart around the operating facilities of the site. Each station is equipped with a membrane filter that is changed weekly and analyzed for gross alpha and gross beta-gamma.

Alpha Concentration:

Weekly Maximum, 7.93 x 10-15 ).I.Ci/cc Weekly Average, 1.36 x 10-15 ).I.Ci/cc Beta Concentration:

Weekly Maximum, 6.58 x 10-14 ).I.Ci/cc Weekly Average, 1.49 x 10-14 ).I.Ci/cc 3.3 Gamma Radiation The yearly dose results for the year 2015 as determined from evaluation of site perimeter environmental monitoring dosimeters showed no departure from normal stable backgrounds.

3.4 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.

3.5 Off-Site Samples taken off the site indicate normal background for the area.

Page 2 of 3

GETR Annual Report No. 57 4.0 ACTIVITIES Routine inspections were conducted during this report period. There were no preventive or corrective maintenance activities performed having safety significance during the reporting period.

5.0 ORGANIZATION The organizational structure remained unchanged during 2015. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager.

Regulatory Compliance and EHS remai~s T. M. Leik.

6.0 CONCLUSION

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

GE Hitachi Nuclear Energy Vallecitos Operations T.A. Caine Manager Vallecitos Nuclear Center Jtogl3 of3

_j

Attachment 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signature on original at GEH Vallecitos C-017 HITACHI LOCATION DATE:

VALLECITOS NUCLEAR CENTER 11/14115 TIME:

NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 1 of2) 1300 REASON IRI Routine 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item ll 1 n TOTAL Distance llY llY a a llY py a a No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 2

1 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 em 2

2 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOem 2

3 Personnel Air Lock SOP <100 <500 <20 <200 IOOem 2

4 1st Floor - Clean Area * <I <I F <100 <500 <20 <200 100 em 2

5 -Zone Area* <1-8 <1-8 F 300 1500 <20 <200 100 em 6 2nd Floor- General Dose Rate <1-2 <1-2 F 7 - EEHS Cubicle Door 7 7 c 8 - Field Reading Around EEHS Cubicle 1.5-5 1.5-5 F 2

9 - Floor Smear I Clean Area * <100 <500 <20 <200 100 em 10 - Filter Bank <I <I c 2

11 3rd Floor- Zone Area North I Floor* <1-4 <1-4 F 2200 11000 <20 <200 100 em 2

12 - Zone Area South <I <I F <100 <500 <20 <200 100 em 2

13 - Bridge I Canal 1.5 1.5 F 200 1000 <20 <200 100 em 2

14 - Missile Shield Point A* <I <I F <100 <500 <20 <200 100cm 2

15 -Platform <0.5 <0.5 F <100 <500 <20 <200 100 em 2

16 - Clean Area * <0.5 <0.5 F <100 <500 <20 <200 100 em INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM- E -120 RM- RM- PAC-1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE py PANCAKE 20% X COMMENTS

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

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

NEO 289 (REV. 07/10)

Attachment 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signature on original at GEH Vallecitos C-017 8 HITACHI LOCATION DATE:

11/14115 VALLECITOS NUCLEAR CENTER TIME:

NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of 2) 1300 REASON 00 Routine D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item Jl T n TOTAL Distance Jlr llr a a llr Jlr a a No. mRadlh mR/h mRemlh mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 3rd Floor- Zone Area Floor Drain 40 6 46 c 2

2 Elevator <0.5 <0.5 F <100 <500 <20 <200 100cm 2

3 Basement- Clean Area * <1-3 <1-3 F <100 <500 <20 <200 100cm 4 - Filter Bank I I F 2

5 -Zone Area* <1-5 <1-5 F 100 500 <20 <200 100 cm 6 - Control Rod Storage 1.0-50 1.0-50 c 7 - Control Rod Repair Hood <1-3 <1-3 F-C 8 - Autoclave I Rod Work Area <I <I c 2

9 Mezzanine between 2nd & 3rd Floors <0.5 <0.5 F <100 <500 <20 <200 100 cm 10 11 First Floor Zone - hot spot on floor** 180 70 250 c 20000 100000 <20 <200 100 em 2

12 13 14 15 16 INSTRUMENT USED PRM -7 CP-5 R0-20 PNR-4 TBM- E -120 RM- RM- PAC -1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE py PANCAKE 20% X COMMENTS

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

• • Gamma Spectroscopy indicates this is Cs-137 (4 p (4 p GEO.) GEO.)

NEO 289 (REV. 07/10)

ATIACHMENTZ: Air Sample Data for Vallecitos Reactor Annual Inspection 2015 Initial 1 Hour Decay 48 Hour Decay

• Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (mil ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 2210.45 1.02E-09 5887.16 2.73E-09 978.99 4.50E-10 352.75 1.62E-10 0.27 1.24E-13 179.69 8.33E-11 Basement 2.83E+06 2039.96 9.38E-10 5281.56 2.45E-09 639.56 2.94E-10 1373.31 6.32E-10 0.70 3.22E-13 21.14 9.80E-12 Fuel Pool 2.83E+06 2067.26 9.51E-10 5297.21 2.46E-09 1096.67 5.04E-10 2440.18 1.12E-09 0.90 4.14E-13 9.42 4.37E-12 EVESR First Floor 2.83E+06 5163.65 2.38E-09 14342.86 6.65E-09 3180.74 1.46E-09 7079.93 3.26E-09 0.60 2.76E-13 1.15 5.33E-13 Basement 2.83E+06 6219.82 2.86E-09 16754.30 7.77E-09 2553.03 1.17E-09 5429.47 2.50E-09 0.40 1.84E-13 14.87 6.89E-12 519' Level 2.83E+06 6213.91 2.86E-09 16797.99 7.79E-09 3347.47 1.54E-09 7481.06 3.44E-09 0.80 3.68E-13 4.33 2.01E-12 GETR First Floor 2.83E+06 971.07 4.47E-10 2391.69 1.11E-09 452.53 2.08E-10 965.12 4.44E-10 0.20 9.20E-14 5.40 2.50E-12 Basement 2.83E+06 937.69 4.31E-10 2319.45 1.08E-09 464.01 2.13E-10 1041.09 4.79E-10 0.30 1.38E-13 3.19 1.48E-12 Third Floor 2.83E+06 808.45 3.72E-10 1955.49 9.06E-10 65.78 3.03E-11 131.32 6.04E-11 0.50 2.30E-13 14.26 6.61E-12 Tennelec System "A" Efficiency & Conversion Factors

• Note: Lack of P10 gas prevented 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> count.

Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Sampling Information Flow Minutes Rate Total Total Sam~le 3

Reactor location Date Sam~led Time On Time Off sam~led (dm) Flow(fe) ml/ft Volume (ml)

VBWR First Floor 11/14/2015 7:00 7:20 20 5 100.0 28317 2.83E+06 VBWR Basement 11/14/2015 7:40 8:00 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/14/2015 7:20 7:40 20 5 100.0 28317 2.83E+06 EVESR First Floor 11/14/2015 8:35 8:55 20 5 100.0 28317 2.83E+06 EVESR Basement 11/14/2015 9:25 9:45 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/14/2015 9:00 9:20 20 5 100.0 28317 2.83E+06 GETR First Floor 11/14/2015 11:35 11:55 20 5 100.0 28317 2.83E+06 GETR Basement 11/14/2015 12:00 12:20 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/14/2015 12:25 12:45 20 5 100.0 28317 2.83E+06

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

ANNUAL REPORT NO. 51 FOR THE VEAR 2015 LICENSE DPR-1 DOCKET 50-18 MARCH 2016

VBWR Annual Report No. 51 Vallecitos Boiling Water Reactor (Deactivated)

I

• Annual Report No. 51 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor IVBWR) in a deactivated status under the authority of Amendment No. 21 to License DPR-1, Docket 1 lo r ..11 o

50-18, issued Oct 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2015 to December 31, 2015 is presented, as required by paragraph 5.d.2 of the license.

1.0

SUMMARY

,r 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.

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

Page 1 af 2

VBWR Annual Report No. 51 5.0 ORGANIZATION The organizational structure remained unchanged during 2015. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager. Regulatory Compliance and EHS remains T. M. Leik.

6.0 CONCLUSION

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

GE Hitachi Nuclear Energy Vallecitos Operations T.A. Caine Manager Vallecitos Nuclear Center f!Ogt2of2

Attachment 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signature on original at GEH Vallecitos D-054 8 HITACHI LOCATION DATE:

11/14/15 VALLECITOS NUCLEAR CENTER TIME:

NUCLEAR SAFETY SURVEY RECORD VBWR Containment 0800 REASON 1:&1 Routine 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item ll 1 n TOTAL Distance llr jly a a jly Jly a a No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 2

1 Main Floor- General Area <0.5 <0.5 F <100 <500 <20 <200 100 em 2

2 - Area Over Reactor Vessel <0.5 <0.5 F <100 <500 <20 <200 100 cm 3

2 4 Basement- General Area <1 <1 F <100 <500 <20 <200 100 cm 5 -Sump 2 5 7 c 150 750 <20 <200 100 cm 2

6 2

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

2 9 Top of Fuel Pool <0.5 <0.5 F <100 <500 <20 <200 100 cm 10 l

11 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOcm 12 2

13 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 cm 14 15 16 INSTRUMENT USED PRM -7 CP - 5 R0 - 20 PNR-4 TBM- E -120 RM- RM- PAC-1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: {circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC- 3A {U) 10% X PROBE py PANCAKE 20% X COMMENTS EFF . a 43-4 {U) 10% EFF.

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

NEO 289 {REV. 0711 0)

AITACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2015 Initial 1 Hour Decay 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 ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 2210.45 1.02E-09 5887.16 2.73E-09 978.99 4.50E-10 352.75 1.62E-10 0.27 1.24E-13 179.69 8.33E-11 Basement 2.83E+06 2039.96 9.38E-10 5281.56 2.45E-09 639.56 2.94E-10 1373.31 6.32E-10 0.70 3.22E-13 21.14 9.80E-12 Fuel Pool 2.83E+06 2067.26 9.51E-10 5297.21 2.46E-09 1096.67 5.04E-10 2440.18 1.12E-09 0.90 4.14E-13 9.42 4.37E-12 EVESR First Floor 2.83E+06 5163.65 2.38E-09 14342.86 6.65E-09 3180.74 1.46E-09 7079.93 3.26E-09 0.60 2.76E-13 1.15 5.33E-13 Basement 2.83E+06 6219.82 2.86E-09 16754.30 7.77E-09 2553.03 1.17E-09 5429.47 2.50E-09 0.40 1.84E-13 14.87 6.89E-12 519' Level 2.83E+06 6213.91 2.86E-09 16797.99 7.79E-09 3347.47 1.54E-09 7481.06 3.44E-09 0.80 3.68E-13 4.33 2.01E-12 GETR First Floor 2.83E+06 971.07 4.47E-10 2391.69 1.11E-09 452.53 2.08E-10 965.12 4.44E-10 0.20 9.20E-14 5.40 2.50E-12 Basement 2.83E+06 937.69 4.31E-10 2319.45 1.08E-09 464.01 2.13E-10 1041.09 4.79E-10 0.30 1.38E-13 3.19 1.48E-12 Third Floor 2.83E+06 808.45 3.72E-10 1955.49 9.06E-10 65.78 3.03E-11 131.32 6.04E-11 0.50 2.30E-13 14.26 6.61E-12 Tennelec System "A" Efficiency & Conversion Factors

• Note: Lack of P10 gas prevented 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> count.

Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Sampling Information Flow Minutes Rate Total Total Sam~le 3 3 Reactor Location Date Sam~led Time On Time Off sam~led (cfm) Flow (ft } ml/ft Volume (ml}

VBWR First Floor 11/14/2015 7:00 7:20 20 5 100.0 28317 2.83E+06 VBWR Basement 11/14/2015 7:40 8:00 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/14/2015 7:20 7:40 20 5 100.0 28317 2.83E+06 EVESR First Floor 11/14/2015 8:35 8:55 20 5 100.0 28317 2.83E+06 EVESR Basement 11/14/2015 9:25 9:45 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/14/2015 9:00 9:20 20 5 100.0 28317 2.83E+06 GETR First Floor 11/14/2015 11:35 11:55 20 5 100.0 28317 2.83E+06 GETR Basement 11/14/2015 12:00 12:20 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/14/2015 12:25 12:45 20 5 100.0 28317 2.83E+06

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

ANNUAL REPORT NO. 48 FOR THE VEAR 2015 LICENSE DR-10 DOCKET 50-183 MARCH 2016

EVESR Annual Report No. 48 ESADA-Vallecitos Experimental Superheat Reactor (Deactivated)

ANNUAL REPORT NO. 48 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, 2015 to December 31, 2015 is presented, as required by Amendment 7, Appendix A. Technical Specifications, section C. 1.

1.0 SUMMARV 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.

4.0 ACTIVIT! ES Routine inspections were conducted during this report period.

The equipment disposal concluded during 2010.

Page 1 of 2

EVESR Annual Report No. 48 5.0 ORGANIZATION The organizational structure remained unchanged during 2015. The S1te Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager.

Regulatory Compliance and EHS remains T. M. Leik.

6.0 CONCLU~ION GE Hitachi Nuclear Energy concludes that the deactivated ESADA-Vollecitos Experimental Superheat Reactor is being maintained in o safe shutdown condition.

The inspections, access control, and administratively controlled activities ensure maximum protection for the public health and safety. The procedures will be continued to maintain this high level of protection.

GE Hitachi Nuclear Energy Vallecitos Operations T.A.Caine Manager Vallecitos Nuclear Center

Attachment 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signature on original at GEH Vallecitos D-055 HITACHI LOCATION DATE:

VALLECITOS NUCLEAR CENTER 11/14/15 TIME:

NUCLEAR SAFETY SURVEY RECORD EVESR Containment 0900 REASON 1:&1 Routine 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item p y n TOTAL Distance py py a a py py a a No. mRad/h mRih mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 2

1 Top of Spent Fuel Pool (Main Floor) <0.5 <0.5 F <100 <500 <20 <200 100 em 2

2 3 487' Level (Basement) <I <I F 200 1000 <20 <200 100 cm 2

4 503' Level <0.5 <0.5 F <100 <500 <20 <200 100 em 5 519' Level <0.5 <0.5 c 100 500 <20 <200 100 cm 2

6 534' Level - General Area <1-1.5 <1-1.5 c 500 2500 <20 <200 100 cm 2

7 - Floor Drain 7 7 F 8 - Emergency Cooling Valves 1-4 1-4 c 2

9 549' Level <0.5 <0.5 F 100 500 <20 <200 100 cm 10 2

11 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 cm 2

12 Personnel Air Lock <0.5 <0.5 F 100 500 <20 <200 IOOcm 13 14 15 16 INSTRUMENT USED PRM

• 7 CP - 5 R0-20 PNR-4 TBM- E -120 RM- RM- PAC -1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC- 3A (U) 10% X PROBE J3y PANCAKE 20% X OMMENTS EFF. a 43-4 (U) 10% EFF .

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

NEO 289 (REV. 0711 0)

ATIACHMENT 2: Air Sample Data for Vallecitos Reactor Annual Inspection 2015 Initial 1 Hour Decay 48 Hour Decay

• Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (mil ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 2210.45 1.02E-09 5887.16 2.73E-09 978.99 4.50E-10 352.75 1.62E-10 0.27 1.24E-13 179.69 8.33E-11 Basement 2.83E+06 2039.96 9.38E-10 5281.56 2.45E-09 639.56 2.94E-10 1373.31 6.32E-10 0.70 3.22E-13 21.14 9.80E-12 Fuel Pool 2.83E+06 2067.26 9.51E-10 5297.21 2.46E-09 1096.67 5.04E-10 2440.18 1.12E-09 0.90 4.14E-13 9.42 4.37E-12 EVESR First Floor 2.83E+06 5163.65 2.38E-09 14342.86 6.65E-09 3180.74 1.46E-09 7079.93 3.26E-09 0.60 2.76E-13 1.15 5.33E-13 Basement 2.83E+06 6219.82 2.86E-09 16754.30 7.77E-09 2553.03 1.17E-09 5429.47 2.50E-09 0.40 1.84E-13 14.87 6.89E-12 519' Level 2.83E+06 6213.91 2.86E-09 16797.99 7.79E-09 3347.47 1.54E-09 7481.06 3.44E-09 0.80 3.68E-13 4.33 2.01E-12 GETR First Floor 2.83E+06 971.07 4.47E-10 2391.69 1.11E-09 452.53 2.08E-10 965.12 4.44E-10 0.20 9.20E-14 5.40 2.50E-12 Basement 2.83E+06 937.69 4.31E-10 2319.45 1.08E-09 464.01 2.13E-10 1041.09 4.79E-10 0.30 1.38E-13 3.19 1.48E-12 Third Floor 2.83E+06 808.45 3.72E-10 1955.49 9.06E-10 65.78 3.03E-11 131.32 6.04E-11 0.50 2.30E-13 14.26 6.61E-12 Tennelec System "A" Efficiency & Conversion Factors

• Note: Lack of P10 gas prevented 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> count.

Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Sampling Information Flow Minutes Rate Total Total Sam~le 3 3 Reactor Location Date Sam~led Time On Time Off sam~led (cfm) Flow (ft } ml/ft Volume (ml}

VBWR First Floor 11/14/2015 7:00 7:20 20 5 100.0 28317 2.83E+06 VBWR Basement 11/14/2015 7:40 8:00 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/14/2015 7:20 7:40 20 5 100.0 28317 2.83E+06 EVESR First Floor 11/14/2015 8:35 8:55 20 5 100.0 28317 2.83E+06 EVESR Basement 11/14/2015 9:25 9:45 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/14/2015 9:00 9:20 20 5 100.0 28317 2.83E+06 GETR First Floor 11/14/2015 11:35 11:55 20 5 100.0 28317 2.83E+06 GETR Basement 11/14/2015 12:00 12:20 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/14/2015 12:25 12:45 20 5 100.0 28317 2.83E+06

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

ANNUAL REPORT NO. 57 FOR THE YEAR 2015 LICENSE TR-1 DOCKET 50-70 MARCH 2016

GETR Annual Report No. 57 General Electric Test Reactor (Deactivated)

ANNUAL REPORT NO. 57 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. In this annual report, a summary of the status of the facility for the period of January 1, 2015 to December 31, 2015 is presented.

1.0

SUMMARY

The facility remains in essentially the same condition described in Annual Report No. 54. Entry into the reactor building was made for routine radiation surveys and a general examination of conditions throughout the building. The crane, elevator, and ventilation were serviced and tested in 2011 in anticipation of beginning remediation activities. Such activities have not begun.

Radiation and contamination levels remain at acceptable levels. Environmental data is maintained on site and available for review. There were no releases from the stack.

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 2015.

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.

The data below are from sample and dosimeter results accumulated during 2015.

These data are for the entire VNC site and include the effects of operations other than GETR.

Page 1 of 3

GETR Annual Report No. 57 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 not yet fully operational, and the stack air flow has not been calibrated. Thus no concentration data is available for 2015.

3.2 Air Monitors (Yearly average of all meteorological stations.!

Four environmental air-monitoring stations are positioned approximately 90 degrees apart around the operating facilities of the site. Each station is equipped with a membrane filter that is changed weekly and analyzed for gross alpha and gross beta-gamma.

Alpha Concentration:

Weekly Maximum, 7.93 x 10-15 ).I.Ci/cc Weekly Average, 1.36 x 10-15 ).I.Ci/cc Beta Concentration:

Weekly Maximum, 6.58 x 10-14 ).I.Ci/cc Weekly Average, 1.49 x 10-14 ).I.Ci/cc 3.3 Gamma Radiation The yearly dose results for the year 2015 as determined from evaluation of site perimeter environmental monitoring dosimeters showed no departure from normal stable backgrounds.

3.4 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.

3.5 Off-Site Samples taken off the site indicate normal background for the area.

Page 2 of 3

GETR Annual Report No. 57 4.0 ACTIVITIES Routine inspections were conducted during this report period. There were no preventive or corrective maintenance activities performed having safety significance during the reporting period.

5.0 ORGANIZATION The organizational structure remained unchanged during 2015. The Site Manager remains T. A. Caine. The VBWR Facility Manager remains M. R. Schrag. The Manager.

Regulatory Compliance and EHS remai~s T. M. Leik.

6.0 CONCLUSION

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

GE Hitachi Nuclear Energy Vallecitos Operations T.A. Caine Manager Vallecitos Nuclear Center Jtogl3 of3

_j

Attachment 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signature on original at GEH Vallecitos C-017 HITACHI LOCATION DATE:

VALLECITOS NUCLEAR CENTER 11/14115 TIME:

NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 1 of2) 1300 REASON IRI Routine 0 Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item ll 1 n TOTAL Distance llY llY a a llY py a a No. mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 2

1 Personnel Air Lock <0.5 <0.5 F <100 <500 <20 <200 100 em 2

2 Equipment Air Lock <0.5 <0.5 F <100 <500 <20 <200 IOOem 2

3 Personnel Air Lock SOP <100 <500 <20 <200 IOOem 2

4 1st Floor - Clean Area * <I <I F <100 <500 <20 <200 100 em 2

5 -Zone Area* <1-8 <1-8 F 300 1500 <20 <200 100 em 6 2nd Floor- General Dose Rate <1-2 <1-2 F 7 - EEHS Cubicle Door 7 7 c 8 - Field Reading Around EEHS Cubicle 1.5-5 1.5-5 F 2

9 - Floor Smear I Clean Area * <100 <500 <20 <200 100 em 10 - Filter Bank <I <I c 2

11 3rd Floor- Zone Area North I Floor* <1-4 <1-4 F 2200 11000 <20 <200 100 em 2

12 - Zone Area South <I <I F <100 <500 <20 <200 100 em 2

13 - Bridge I Canal 1.5 1.5 F 200 1000 <20 <200 100 em 2

14 - Missile Shield Point A* <I <I F <100 <500 <20 <200 100cm 2

15 -Platform <0.5 <0.5 F <100 <500 <20 <200 100 em 2

16 - Clean Area * <0.5 <0.5 F <100 <500 <20 <200 100 em INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM- E -120 RM- RM- PAC-1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE py PANCAKE 20% X COMMENTS

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

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

NEO 289 (REV. 07/10)

Attachment 1 SURVEYOR (print and sign) IREVIEWER NO.

Name and signature on original at GEH Vallecitos C-017 8 HITACHI LOCATION DATE:

11/14115 VALLECITOS NUCLEAR CENTER TIME:

NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of 2) 1300 REASON 00 Routine D Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item Jl T n TOTAL Distance Jlr llr a a llr Jlr a a No. mRadlh mR/h mRemlh mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1 3rd Floor- Zone Area Floor Drain 40 6 46 c 2

2 Elevator <0.5 <0.5 F <100 <500 <20 <200 100cm 2

3 Basement- Clean Area * <1-3 <1-3 F <100 <500 <20 <200 100cm 4 - Filter Bank I I F 2

5 -Zone Area* <1-5 <1-5 F 100 500 <20 <200 100 cm 6 - Control Rod Storage 1.0-50 1.0-50 c 7 - Control Rod Repair Hood <1-3 <1-3 F-C 8 - Autoclave I Rod Work Area <I <I c 2

9 Mezzanine between 2nd & 3rd Floors <0.5 <0.5 F <100 <500 <20 <200 100 cm 10 11 First Floor Zone - hot spot on floor** 180 70 250 c 20000 100000 <20 <200 100 em 2

12 13 14 15 16 INSTRUMENT USED PRM -7 CP-5 R0-20 PNR-4 TBM- E -120 RM- RM- PAC -1SA LUDLUM-12 SERIAL NUMBER 285 1339 897 Area Posted: (circle applicable) RA HRA CA RMA AIRBORNE PROBE a AC-3A (U) 10% X PROBE py PANCAKE 20% X COMMENTS

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

• • Gamma Spectroscopy indicates this is Cs-137 (4 p (4 p GEO.) GEO.)

NEO 289 (REV. 07/10)

ATIACHMENTZ: Air Sample Data for Vallecitos Reactor Annual Inspection 2015 Initial 1 Hour Decay 48 Hour Decay

• Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume (mil ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml ncpm uCi/ml VBWR First Floor 2.83E+06 2210.45 1.02E-09 5887.16 2.73E-09 978.99 4.50E-10 352.75 1.62E-10 0.27 1.24E-13 179.69 8.33E-11 Basement 2.83E+06 2039.96 9.38E-10 5281.56 2.45E-09 639.56 2.94E-10 1373.31 6.32E-10 0.70 3.22E-13 21.14 9.80E-12 Fuel Pool 2.83E+06 2067.26 9.51E-10 5297.21 2.46E-09 1096.67 5.04E-10 2440.18 1.12E-09 0.90 4.14E-13 9.42 4.37E-12 EVESR First Floor 2.83E+06 5163.65 2.38E-09 14342.86 6.65E-09 3180.74 1.46E-09 7079.93 3.26E-09 0.60 2.76E-13 1.15 5.33E-13 Basement 2.83E+06 6219.82 2.86E-09 16754.30 7.77E-09 2553.03 1.17E-09 5429.47 2.50E-09 0.40 1.84E-13 14.87 6.89E-12 519' Level 2.83E+06 6213.91 2.86E-09 16797.99 7.79E-09 3347.47 1.54E-09 7481.06 3.44E-09 0.80 3.68E-13 4.33 2.01E-12 GETR First Floor 2.83E+06 971.07 4.47E-10 2391.69 1.11E-09 452.53 2.08E-10 965.12 4.44E-10 0.20 9.20E-14 5.40 2.50E-12 Basement 2.83E+06 937.69 4.31E-10 2319.45 1.08E-09 464.01 2.13E-10 1041.09 4.79E-10 0.30 1.38E-13 3.19 1.48E-12 Third Floor 2.83E+06 808.45 3.72E-10 1955.49 9.06E-10 65.78 3.03E-11 131.32 6.04E-11 0.50 2.30E-13 14.26 6.61E-12 Tennelec System "A" Efficiency & Conversion Factors

• Note: Lack of P10 gas prevented 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> count.

Alpha Efficiency 34.58%

Beta Efficiency 34.32%

dpm/uCi 2.22E+06 Alpha cpm/uCi 7.68E+05 Beta cpm/uCi 7.62E+05 Sampling Information Flow Minutes Rate Total Total Sam~le 3

Reactor location Date Sam~led Time On Time Off sam~led (dm) Flow(fe) ml/ft Volume (ml)

VBWR First Floor 11/14/2015 7:00 7:20 20 5 100.0 28317 2.83E+06 VBWR Basement 11/14/2015 7:40 8:00 20 5 100.0 28317 2.83E+06 VBWR Fuel Pool 11/14/2015 7:20 7:40 20 5 100.0 28317 2.83E+06 EVESR First Floor 11/14/2015 8:35 8:55 20 5 100.0 28317 2.83E+06 EVESR Basement 11/14/2015 9:25 9:45 20 5 100.0 28317 2.83E+06 EVESR 519' Level 11/14/2015 9:00 9:20 20 5 100.0 28317 2.83E+06 GETR First Floor 11/14/2015 11:35 11:55 20 5 100.0 28317 2.83E+06 GETR Basement 11/14/2015 12:00 12:20 20 5 100.0 28317 2.83E+06 GETR Third Floor 11/14/2015 12:25 12:45 20 5 100.0 28317 2.83E+06