ML16300A120
| ML16300A120 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos File:GEH Hitachi icon.png |
| Issue date: | 10/26/2016 |
| From: | Caine T Hitachi-GE Nuclear Energy, Ltd |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| TAC 16-014 | |
| Download: ML16300A120 (8) | |
Text
.
) HITACHI TAC 16-014 October 26. 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington. D. C. 20555-001 GE Hitachi Nuclear Energy Thomas A. Caine Site Manager.
Vallecitos Nuclear Center 6705 Vallecitos Rd Sunol. CA 94586 USA T 925 918 6018 Thamas.caine@ge.cam
Subject:
GEH Annual Shutdown Reactor Report for 2016-GETR Revision 1
References:
- 1) Docket 50-70 (GETR)
- 2) Letter T. A. Caine to NRC Document Control Desk, "GEH Annual Shutdown Reactor Reports for 2016, 3/22/16 Enclosed is a revised 2016 Annual Report for the deactivated 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,
- f. A.~
Tom Caine, Manager Vallecitos Nuclear Center
Enclosure:
GETR Annual Report No. 57, Revision 1 Commitments: None cc: NRC Region IV Administrator J. Parrott. NRC NMSS
) HITACHI GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)
ANNUAL REPORT NO. 57 FOR THE YEAR 2015 LICENSE TR-1 DOCKET 50-70 REVISION 1 OCTOBER 2016 Vallecitos Nuclear Center Sunol, California
GETR Annual Report No. 57 General Electric Test Reactor (Deactivated)
ANNUAL REPORT NO. 57 REVISION 1 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.
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 REVISION 1 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. and the stack air flow has been calibrated.
Alpha Concentration 1.11 x 10-15 )lCi/cc Beta Concentration 3.09 x 10-15 )lCi/cc 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, Weekly Average, Beta Concentration:
Weekly Maximum.
Weekly Average, 3.3 Gamma Radiation 7.93 x 10-15 )lCi/cc 1.36 x 10-15 )lCi/cc 6.58 x 10-14 )lCi/cc 1.49 x 10-14 )lCi/cc 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 REVISION 1 4.0 ACTIVIT! ES 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 remains 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 Page 3 of 3
At t achment 1 SURVEYOR (print and sign)
I REVIEWER NO.
HITACHI Name and signature on original at GEH Vallecitos C-01 7 LOCATION DATE:
VALLECITOS NUCLEAR CENTER 11 /14115 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page I of2)
TIME:
1300
[8] Routine REASON 0
Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item fl y
n TOTAL Distance fl y fl y a
[l py fly u
u No.
mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1
Personnel Air Lock
<0.5
<0.5 F
< 100
<500
<20
<200 100 Cl112 2
Equipment Air Lock
<0.5
<0.5 F
< 100
<500
<20
<200 I 00 cm2 3
Personnel Air Lock SOP
< 100
<500
<20
<200 100 cm2 4
1st Floor-Clean Area *
< l
< I F
< 100
<500
<20
<200 100 cm2 5
-Zone Area*
< 1-8
< l-8 F
300 1500
<20
<200 100 cm2 6
2nd Floor -General Dose Rate
< 1-2
< l -2 F
7
- EEHS Cubicle Door 7
7 c
8
- Field Reading Around EEHS Cubicle 1.5-5 1.5-5 F
9
- Floor Smear I Clean Area *
< 100
<500
<20
<200 I 00 cm2 10
- Filter Bank
< l
< l c
11 3rd Floor - Zone Area North I Floor*
< l -4
< l-4 F
2200 11 000
<20
<200 I 00 cm2 12
- Zone Area South
< l
< l F
< 100
<500
<20
<200 100 Cl112 13
- Bridge I Canal 1.5 1.5 F
200 1000
<20
<200 100cm 2 14
- Missile Shield Point A*
< l
< I F
< 100
<500
<20
<200 I 00 cm2 15
-Platform
<0.5
<0.5 F
< 100
<500
<20
<200 100 cnl 16
- Clean Area *
<0.5
<0.5 F
< 100
<500
<20
<200 100 Cll12 INSTRUMENT USED PRM - 7 CP-5 RO-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 BY PANCAKE 20%
X COMMENTS a 43-4 (U) 10%
- Whatman Smears EFF.
EFF.
(4 p (4 p GEO.)
GEO.)
NEO 289 (REV. 07/1 0)
SURVEYOR (print and sign)
I REVIEWER NO.
e HITACHI Name and signature on original at GEH Vallecitos C-0 17 LOCATION DATE:
VALLECITOS NUCLEAR CENTER II / 14/15 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of2)
TIME:
1300
[8] Routine REASON 0
Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item fl
'/
n TOTAL Distance fl y fl *r a
a fl y fl y a
a No.
mRad/h mR/h mRem/h mRem/h CPM dPM CPM dPM CPM dPM CPM dPM AREA 1
3rd Floor - Zone Area Floor Drain 40 6
46 c
2 Elevator
<0.5
<0.5 F
< tOO
<500
<20
<200 I 00 cm2 3
Basement-Clean Area *
< 1-3
< t-3 F
< t OO
<500
<20
<200 I 00 cm 2 4
- Filter Bank t
I F
5
-Zone Area*
< t -5
< 1-5 F
t OO 500
<20
<200 100 Cll12 6
- Control Rod Storage l.0-50 t.0-50 c
7
-Cont rol Rod Repair Hood
< t-3
< 1-3 F-C 8
- Autoclave I Rod Work Area
< I
< I c
9 Mezzanine between znd & 3'd Floors
<0.5
<0.5 F
< tOO
<500
<20
<200 I 00 cm2 10 11 First Floor Zone - hot spot on floor**
180 70 250 c
20000 tOOOOO
<20
<200 100 cm 2 12 13 14 15 16 INSTRUMENT USED PRM -7 CP-5 RO-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 a 43-4 (U) 10%
- Whatman Smears EFF.
EFF.
- Gamma Spectroscopy indicates this is Cs-137 (4 p (4 p GEO.)
GEO.)
NEO 289 (REV. 07/10)
ATTACHMENT 2:
Air Sample Data for Vallecitos Reactor Annual Inspection 2015 Initial 1 Hour Decay Sample Alpha Beta Alpha Beta Reactor Location Volume !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 Basement 2.83E+06 2039.96 9.38E-10 5281.56 2.45E-09 639.56 2.94E-10 1373.31 6.32E-10 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 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 Basement 2.83E+06 6219.82 2.86E-09 16754.30 7.77E-09 2553.03 1.17E-09 5429.47 2.50E-09 519' Level 2.83E+06 6213.91 2.86E-09 16797.99 7.79E-09 3347.47 1.54E-09 7481.06 3.44E-09 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 Basement 2.83E+06 937.69 4.31E-10 2319.45 1.08E-09 464.01 2.13E-10 1041.09 4.79E-10 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 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.
Reactor VBWR VBWR VBWR EVESR EVESR EVESR GETR GETR GETR Alpha Efficiency 34.58%
Beta Efficiency dpm/uCi Alpha cpm/uCi Beta cpm/uCi Location First Floor Basement Fuel Pool First Floor Basement 519' Level First Floor Basement Third Floor 34.32%
2.22E+06 7.68E+05 7.62E+05 Date Sam~led 11/14/2015 11/14/2015 11/14/2015 11/14/2015 11/14/2015 11/14/2015 11/14/2015 11/14/2015 11/14/2015 Time On 7:00 7:40 7:20 8:35 9:25 9:00 11:35 12:00 12:25 Sampling Information Flow Minutes Rate Total Total Sam~le Time Off sam~led (cfm)
Flow {tel mllte Volume (ml}
7:20 20 5
100.0 28317 2.83E+06 8:00 20 5
100.0 28317 2.83E+06 7:40 20 5
100.0 28317 2.83E+06 8:55 20 5
100.0 28317 2.83E+06 9:45 20 5
100.0 28317 2.83E+06 9:20 20 5
100.0 28317 2.83E+06 11:55 20 5
100.0 28317 2.83E+06 12:20 20 5
100.0 28317 2.83E+06 12:45 20 5
100.0 28317 2.83E+06 48 Hour Decay*
Alpha Beta ncpm uCi/ml ncpm uCi/ml 0.27 1.24E-13 179.69 8.33E-11 0.70 3.22E-13 21.14 9.80E-12 0.90 4.14E-13 9.42 4.37E-12 0.60 2.76E-13 1.15 5.33E-13 0.40 1.84E-13 14.87 6.89E-12 0.80 3.68E-13 4.33 2.01E-12 0.20 9.20E-14 5.40 2.50E-12 0.30 1.38E-13 3.19 1.48E-12 0.50 2.30E-13 14.26 6.61E-12