ML19087A125

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GE-Hitachi Nuclear Energy Americas, LLC - Annual Shutdown Reactor Reports for the Year 2018
ML19087A125
Person / Time
Site: Vallecitos Nuclear Center, Vallecitos
Issue date: 03/27/2019
From: Feyrer M
GE-Hitachi Nuclear Energy Americas
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
M190066
Download: ML19087A125 (18)


Text

HITACHI M190066 March 27,2019 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-001 GE Hitachi Nuclear Energy Matt J. Feyntr Site Manaser.

Vallecitos Nuclear Center 6705 VallecitDs Rd Sunol, CA 94586 USA T 925 918 6018 Matt.feyrer@lse.an

Subject:

GEH Annual Shutdown Reactor Reports for the Year 2018

Reference:

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

Enclosed are the 2019 Annual Reports for the deactivated Reactors (Vallecitos Bolling Water Reactor (VBWR), ESADA-Vallecltos Experimental Superheat Reactor (EVESR),

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

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

Matt Feyrer, Site Manager Vallecitos Nuclear Center

Enclosures:

VBWR Annual Report No. 54, EVESR Annual Report No. 51, and GETR Annual Report No. 60 cc: NRC Region IV Adminis~rator J. Parrott, NRC NMSS MJF 19-Q05

Enclosures VBWR Annual Report No. 54 EVESR Annual Report No. 51 G.ETR Annual Report No. 60

HITACHI C r !'*

  • I. ['(*-*, l~ f. **

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  • t J,. I c: I VALLECITOS BOIUNG WATER REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 54 FOR THE YEAR 2018 LICENSE DPR-1 DOCKET 50-18 MARCH2019 Vaii<<<tos Nudear Center Sunol, Collforn/a

VBWR Annual Report No. 54 Vallecitos Boiling Water Reactor (Deactivated)

Annual Report No. 54 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWR) In a deactivated status under the authority of Amendment No. 21 to Ucense 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, 2018 to December 31, 2018 is presented, as required by paragraph S.d.2 of the license.

1.0

SUMMARY

Entry Into the containment building was made for routine radiation surveys and a general examination of conditions throughout the building.

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. 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. No equipment removal occurred in 2018.

3.0 RADIATION AND CONTAMINATION Complete radiation anCI contanunatlon surveys orfl;_e_z-taciffty Indicate l tlat levels remarn-loW: -

Results of the surveys are presented in attachment 1. Air sampling results are presented il:l attachment 2. The radiation/contamination levels listed are representative but not necessarily maximum values.

A supplement to the 2017 Annual Report was submitted on June, 20, 2018 that included information related to water found in the VBWR containment building basement during the 2017 annual inspection. On September, 19, 2018, the NRC Issued a Severity Level IV violation (NOV) In Inspection Report 050-00018/2018-001; 050*00070/2018-001; 050-00183/2018-001 (ML18261A410) for failing to follow site Procedure 6.2, Patrols and Inspections, Revision 7.

VNC responded In writing on October 19, 2018 (Ml18292A751) and provided supplemental written information on January 23, 2019 (MU9023A306). The NRC completed a review of all Page 1of2

VBWR Annual Report No. 54 provided information, concluded that completed and proposed corrective actions adequately addressed regulatory noncompliance as described in the NOV, and so notified VNC of closure of the NOV in writing on January 25, 2019 (Ml18346A704}.

4.0 Aatvmes Routine inspections were conducted during this report period. No reactor equipment was removed, and no safety significant preventive or corrective maintenance activities were performed In 2018. As noted on the attached survey report dated September 13, 2018, approximately one Inch of water was found to be present on the basement floor. Responsive actions established by CRII28719 include the following:

A scale was installed to facilitate monitoring water level changes The inspection frequency was temporarily increased Water was sampled and then transferred to the wastewater processing plant via the basement Sump pump.

A hard-plumbed system was installed to transfer water from the sump to a holding tank where the water will be sampled and transferred to the site waste processing plant.

5.0 ORGANIZATION The organizational structure changed during 2018. The Site Manager remains M. J. Feyrer. The VNC site Facility Manager changed from M. R. Schrag to K. P. Zanotto. The Manager, Regulatory Compliance and Environmental Health and Safety, T. M. lelk, retired January 2018 and has been replaced by J. Smyly.

6.0 CONCLUSION

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

GE Hitachi Nuclear Energy Vallecitos Operations M. J.

yr r Manager Valleci os Nuclear Center Page 2of2

A I I A(.;HMt:N I 1: AnnUal ::surveys SURVEYOR (print and sign)

JREVIEWER NO.

... HITACHI Name and signatures on Original at OEH Vallecitos D-040 LOCATION DATE:

VALLECITOS NUCLEAR CENTER 09/13118 NUCLEAR SAFETY SURVEY RECORD VBWR Containment TIME:

1000 mJ Routine REASON 0

Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item m~

n TOTAL Distance ~

py a

a p.,

py a

a No.

mRih mRM!It mRamlh dPM CPM dPM CPM dPM cPM dPM AREA 1 Main Floor - General Area

<1

<1 F

<100

<500

<20

<200 100 cm2 2

- Area Over Reactor Vessel

<I

<I F

<100

<SOO

<20

<200 100cm2 3

4 Basement-General Area

<I

<I F

<100

<SOO

<20

<200 100cm2 5

-Sump

<I

<I c

<100

<SOO

<20

<200 100cm2 6

7 Reactor Vessel Head Area

<I

<I F

<too* <500

<20

<200 lOOcm 8

9 Top ofFuel Pool

<1

<I F

<100

<500

<20

<200 lOOcm' 10 11 Personnel Air Lock

<I

<I F

<100

<500

<20

<200 100 em' 12 13 Equipment AirLock

<1

<I F

<100

<500

<20

<200 IOOcm 14 15 16 INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM-E-120 RM-14 RM-15 PAC-1SA LUDLUM-12 SERIAL NUMBER 285 1022 825 Area Posted: (clmle applicable)~

,!IRA(£~~

AIRBORNE PROBE a AC-3A (U) 10% *X PROBE Jly PANCAKE 20%

X COMMENTS There is approximaterly I inch of water in basement floor.

EFF.

u 43-4 (U) 10%

EFF.

(4P (4P GEO.)

GEO.)

NEO 289 (REV. 07/10)

ATTACHMENT 2:

Air Sample Data for Vallecitos Reactor Annuall_nspectlon 2018 Initial lHourDecay

>24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor location Volume(mll

!!9!!!1 uCI/ml ncpm uCI/ml

!!Sm1 uCI/ml

!!Sm1 uCI/ml

!!SI!Dl uCI/ml nmm uCI/ml VBWR First Floor 2.83E+06 1033.52 4.52E-10 2701.42 1.28E-09 132.54 S.SOE-11 291.23 1.27E-10 0.10 4.37E-14 3.45 1.64E-12 Basement 2.83E+06 435.66 1.91E-10 1092.81 5.18E-10 102.95 4.SOE-11 235.53 1.03E-10 1.20 5.25E-13 4.02 1.91E-12 Fuel Pool 2.83E+06 365.41 1.60£-10 896.58 4.25£-10 98.45 4.31£-11 209.25 9.15£-11 0.40 1.75E-13 6.21 2.94E-12 EVESR First Floor 2.83E+06 5773.13 2.53E-09 16093.67 7.63£-09 1164.69 5.10E-10 2344.94 1.03E-09 0.30 1.31E-13 1.33 6.30E-13 Basement 4.96£+06 9234.83 2.31E-09 22113.74 5.99E-09 69230 1.73E-10 1402,02 3.51E-10 0.99 2.47E-13 48.15 1.30E*11 519'level 2.83E+06 4054.53 1.77E-09 10074.52 4.78E-09 95.66 4.19E*11 190.97 8.3SE-11 0.30 1.31E*13 10.63 5.04E*12 GETR First Floor 2.83E+06 749.67 3.28E*10 2013.23 9.54E-10 339.84 1.49E-10 759.32 3.32E-10 0.20 8.75E*14 1.44 6.83E-13 Basement 2.83E+06 495.53 2.17£-10 1263.73 5.99£-10 41.38 1.81E-11 97.71 4.27£-11 1.30 5.69£-13 17.31 8.20E-12 Third Floor 2.83E+06 582.37 2.5SE*10 1524.15 7.22E-10 145.43 6.36E-11 309.95 1.36E-10 1.70 7.44E-13 10.36 4.91E*12 Tennelec System "A" Effldency I& Conversion Factors Alpha *Efficiency 36.3696 Beta Efficiency 33.56%

dpm/uCI 2.22E+06 Alpha cpm/uCI 8.07E+05 Beta cpm/uCI 7.45E+OS Sampling Information Be!!.

!nBI!L 1Hr Al!l!rOX.

Minutes Rate Total Total 5aml!l!

Samele Sa male Minutes Half*Ufe rReactor Location Date ~aml!led IJmeOn nmeoff,

  • saml!led Ccfml Flow(ft~ ~ V!!lyme (ml}

nme Ilm!

~ (min. I VBWR First Floor 9/9/2018 9:40 10:00 20 5

too:o 28317 2.83E+06 10:10 12:00 110 37.1 VBWR Basement 9/13/2018 9:25 9:45 20 5

100.0 28317 2.83E+06 10:05 11:20 75 36.0

_ VBWR Fuel Pool 9/13/2018 9:00 9:20 20 5

100.0 28317 2.83E+06 9:35 10:50 75 39.6 EVESR First Floor.

9/9/2018 10:05 10:25 20 5

100.0 28317 2.83E+06 I 10:35 12:10 95 41.1 EVESR Basement 9/14/2018 10:40 11:15 35 5

175.0 28317 4.96E+06 11:30 13:40 130 34.8 EVESR 519' Level 9/14/2018 10:10 10:30 20 5

100.0 28317 2.83£+06 10:50 13:50 180 33.3 GETR First Floor 9/9/2018 12:03 12:23 20 5

100.0 28317 2.83E+06 12:33 13:23 so 43.8 GETR Basement 9/13/2018 11:05 11:25 20 5

100.0 28317 2.83E+06 11:50 14:05 135 37.7 GETR Third Floor 9/13/2018 11:40 12:00 20 5

100.0 28317 2.83£+06 12:15 13:30 75 37.5

HITACHI ESADA-VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 51 FOR THE YEAR 2018 LICENSE QR-10 DOCKET 50-183 MARCH2019

-,. ' 1: -.

I 'r' Va/IKitos Nud~ Center Sunol, California

EVESR Annual Report No. 51 ESADA-Vallecltos Experimental Superheat Reactor (Deactivated)

ANNUAL REPORT NO. 51 GE Hitachi Nuclear Energy (GEH) has maintained the ESADA Vallecitos Experimental Superheat R~actor (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, 2018 to December 31, 2018 is presented, as required by Amendment 6, license Condition E.2.

1.0

SUMMARY

Entry Into the containment building was made for routine radiation surveys and a general examination of conditions throughout the building.

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. Some reactor equipment has been removed and disposed of as permitted under Amendment 7 of the Technical Specifications. This activity was concluded In 2010 and has not been recommenced. The plugs to the reactor vessel and head storage shield, the wooden cover over the fuel storage pool remain in place. No equipment removal occurred in 2018.

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 ACTNITIES Routine inspections were conducted during this report period. No reactor equipment was removed, and no safety significant preventive or corrective maintenance activities were performed in 2018. As noted on the attached survey dated September 14, 2018, water was noted on the basement floor. Th~ source of the water was determined to be from the ground level dehumidifier condensate. The water was cleaned up during the Inspection.

Page 1 of2

EVESR Annual Report No. 51 5.0 ORGANIZATION The organizational structure changed during 2018. The Site Manager remains M. J.

Feyrer. The VNC site Facility Manager changed from M. R. Schrag to K. P. Zanotto. The Manager, Regulatory Compliance and EHS, T. M. leik, retired January 2018 and has been replaced by J. Smyly.

6.0 CONCLUSION

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

GE Hitachi Nuclear Energy Vallecitos Operations Manager Vallecitos Nuclear Center Page2of2

/"\\I 11'\\\\JniVII::I" I I; 1'\\flnUil::ll "Urv~y::t SURVEYOR (print and sign)

I REVIEWER NO.

fJ HITACHI Name and signatures on Original at GEH Vallecitos D-041 LOCATION DATE:

VALLECITOS NUCLEAR CENTER 09/14/18 NUCLEAR SAFETY SURVEY RECORD EVESR Containment TIME:

11:00 Ill Routme REASON

[J Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECT READING SMEAR READINGS Item II n

TOTAL ~

  • ~

Jly II II 111 liT II II No.

mRadftl mRih mRamlh mRemlh dPM CPM dPM CPM dPM CPM dPM AREA 1 Top of Spent Fuel Pool (Main Floor)

<O.S

<0.5 F

<100

<500

<20

<200 IOOcm' 2

3 487' Level (Basement)

<I

<1 F

<100

<500

<20

<200 100cm' 4

SOl' Level

<I

<1 F

<100

<500

<20

<200 lOOcm' 5 519'Level

<1

<1 F

<100

<SOO

<20

<200 IOOcm' 6 534' Level-General Area I.S I.S F

<100

<500

<20

<200 IOOcm~

7

- Floor Drain 3.5 3.5 c

8

- Emergency Cooling Valves 22 22 c

9 549' Level

<1

<1 F

<100

<500

<20

<200 lOOcm 10 11 l&uipmcnt Air Lock

<O.S

<O.S F

<100

<SOO

<20

<200 lOOcm 12 Personnel Air Lock

<0.5

<O.S F

<100

<500

<20

<200 lOOcm 13 14 15 16

'INSTRUMENT USED PRM-7 CP-5 R0-20 PNR-4 TBM-E-120 RM-14*

RM-15 P~C-1SA LUDLUM-12 SERIAL NUMBER 4549 1022 825 Area Posted: (circle applicable)~ HRA C£&Xj~ AIRBORNE PROSE

a. AC-3A (U) 10%

X PROBE fly PANCAKE 20%

X COMUI!NTS Water found on Basement floor from Condenser on Main Floor EFF.

a. 43-4 (U) 10%

EFF.

(4P (4P i

GEO,)

GEO.)

NEO 289 (REV. 07/10}

ATTACHMENT 2:

Air Sample Data for Vallecitos Reactor Annual Inspection 2018 Initial 1 Hour Decay.

>24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volume(ml) ncpm ucl/ml ncpm uCi/ml

.!l9H!!

uCI/ml ncom Y9Lm!

ncpm uCi/ml

!!9:!!D.

uO/ml VBWR First Floor 2.83E+06 1033.52 4.52E-10 2701.42 1.28E-Q9 132.54 5.80E*ll 291.23 1.27E-10 0.10 4.37E-14 3.45 1.64E-12 Basement 2.83E+06 435.66 1.91E-10 1092.81 5.18E-10 102.95 4.SOE-ll 235.53 1.03E-10 1.20 5.2SE-13 4.02 1.91E-12 Fuel Pool 2.83E+06 365.41 1.60E-10 896.58 4.25E-10 98.45 4.31E-11 209.25 9.15E*ll 0.40 1.7SE-13 6.21 2.94E-12 EVESR First Floor 2.83E+06 5773.13 2.53E-D9 16093.67 7.63E-D9 1164.69 5.10E*10 2344.94 1.03E-09 0.30 1.31E-13 1.33 6.30E-13 Basement 4.96E+06 9234.83 2.31E*09 22113.74 5.99E-D9 692.30 1.73E-10 1402.02 3.51E-10 0.99 2.47E-13 48.15 1.30E-ll 519' Level 2.83E+06 4054.53 1.77E-D9 10074.52 4.78E*09 95.66 4.19E*11 190.97 8.35E-11 0.30 1.31E-13 10.63 5.04E-12 GETR First Floor 2.83E+06 749.67 3.28E-10 2013.23 9.54E-10 339.84 1.49E-10 759.32 3.32E-10 0.20 8.75E-14 1.44 6.83E*13 Basement 2.83E+06 495.53 2.17E-10 1263.73 5.99E-10 41.38 1.81E-11 97.71 4.27E-11 1.30 5.69E*13 17.31 8.20E-12 Third Floor 2.83E+06 582.37 2.55E-10 1524.15 1.221:-10 145.43 6.36E-11 309.95 1.36E-10 1.70 7.44E-13 10.36 4.91E-12 Tennelec System 11A" Efficiency Ia Conversion Factors Alpha Efficiency 36.36%

Beta Efficiency 33.56%

dpm/uCi 2.22E+06 Alpha cpm/uCi 8.07E+05 Beta cpm/uCI 7.45E+05 Samplfna*lnformatlan I

Flaw Initial A am: ox.

Minutes Rate Total Total Samale Samgle Sample Mloutes Half.Ufe Reactor Lacatloo Date Samgled nmeOn nmeOff ~samaled (tfm)

Flaw,lft~

ml/ft1 Volyme (ml).

nme Ilm!

R!S!!

(min.)

VBWR First Floor 9/9/2018 9:40 10:00 20 5

100.0 28317 2.83E+06' 10:10 12:00 110 37.1 VBWR Basement 9/13/2018 9:25 9:45 20 5

10DlD 28317 2.83E+06 10:05 11:20 75 36.0 VBWR Fuel Pool 9/13/2018 9:00 9:20 20 5

100.0 28317 2.83E+06 9:35 10:50 75 39.6 EVESR First Floor 9/9/2018 10:05 10:25 20 5

100.0 28317 2.83E+06 10:35 12:10 95 41.1 EVESR Basement

  • 9/14/2018 10:40 11:15 35 5

175.0 28317 4.96E+06 11:30 13:40 130 34.8 EVESR 519' Level 9/14/2018 10:10 10:30 20 5

100.0 28317 2.83E+06 10:50 13:50 180 33.3 GETR First Floor 9/9/2018 12:03 12:23 20 5

100.0 28317 2.s3E+06 12:33 13:23 so 43.8 GETR Basement 9/13/2018 11:05 11:25 20 5

100.0 28317 2.83E+06 11:50 14:05 135 37.7 GETR Third Floor 9/13/2018 11:40 12:00 20 5

100.0 28317 2.83E+06 12:15 13:30 75 37.5

HITACHI GENERAL ELECTRIC TEST REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 60 FOR THE YEAR 2018 UCENSETR-1 DOCKET 50-70 MARCH2019 Vllll<<<tru N!Khrlr Otnt~tr Sunot Call.(ontlo

GETR Annual Report No. 60 General Electric Test Reactor (Deactivated)

ANNUAL REPORT NO. 60 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, Issu-ed October 22, 2007. In this annual report, a summary of the status of the facility for the period of January 1, 2018 to December 31, 2018 is presented.

l.O

SUMMARY

Entry into the reactor building was made for routine radiation surveys. and a general examination of conditions throughout the building.

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

2.0 STATUS OF FACIUTY In accordance with written procedures, the Facility Manager controls access to the containment building and general systems. No equipment removal occurred in 2018.

The ventilation system remains operable but was not used In 2018.

3.0 RADIATION AND CONTAMINATION Complete radi~tion 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 following analytical results of groundwater samples collected from the B-2 (GETR) well are not included In the site's environmental monitoring program and so are included in this report. Results are typical and representative of background levels. The GETR well was sampled on a semi-annual basis in 2018.

Month Gross beta pCi/L Gross Alpha pCi/L Tritium pCi/L May2018 4.16 15.01 554 November 2018 1.51 1.22 769 Page 1of2

GETR Annual Report No. 60 4.0 ACTIVITIES Routine Inspections were conducted during this report period. No reactor equipment was removed, and no safety significant preventive or corrective maintenance activities were performed in 2018.

5.0 ORGANIZATION The organizational structure changed during 2018. The Site Manager remains M. J.

Feyrer. The VNC Site Facility Manager changed from M. R. Schrag to K. P. Zanotto. The Manager, Regulatory Compliance and EHS, T. M. Leik, retired January 2018 and has been replaced by J. Smyly.

6.0 CONCLUSION

GE Hitachi Nuclear Energy concludes that the deactivated GETR is being maintained In a safe condition. The Inspections, access control, and administratively controlled activities ensure maximum protection for the health and safety of the public. The procedures will be continued to malntai{l this high level of protection.

GE Hitachi Nuclear Energy Vallecitos Operations Manager Vallecitos Nuclear Center Page 2of2

1"\\ I 11"\\wnMII:I, I I; 1"\\rlllUC:III o:IUIVtlly::t SURVEYOR (prfnl and sign)

!REVIEWER NO.

Nam1' and signatures on Original at GEH VaUecitos C-024

  • HITACHI LOCATION DATE:

VALLECITOS NUCLEAR CENTER 09/13/18 NUCLEAR SAFETY SURVEY RECORD 200 Area GE1R Containment (page 1 of2)

TIME:

1230 liD Routine REASON 0

Spacial

~ualSurvey ITEMS OR LOCAnON DOSE RATE DIRECT READING SMEAR READINGS llem p

y n

TOTAL Distanal py Ill ll ll liT ll ll ND.

mRadlh mRih mRamlh mRemlh*

CPM dPM CPM dPM CPM dPM CPM dPM AREA I Personnel Air Lock

<I

<I F

<100

<500

<20

<200 100cm2 2

Equipment Air Lock

<1

<1 F

<100

<500

<20

<200 100 em2 3 Personnel Air Lock SOP

<100

<500

<20

<200 100cm2 4

1st Floor-Clean Area

<I

<1 F

<100

<500

<20

<200 100cm2 s

-Zone Area

<1

<I F

<100

<500

<20

<200 lOOcm 6 2nd Floor-General Dose Rate

<1

<I F

7

- EEHS Cubicle Door 6

6 c

8

- Field Reading Around EEHS Cubicle 5

s F

9

- Floor Smear I Clean Area

<100

<SOO

<20

<200 tOO em 10

- Filter Bank

<I

<I c.

II 3rd Floor-Zone Area North/ Floor l.S l.S F

200 1000

<20

<200 lOOcm" 12

-Zone Area South I

I F

<100

<SOO

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<200 100 em~

13

- Brid_g_e I Canal 1.5 1.5 F

<100

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<20

<200 100cm 14

- Missile Shield Point A

<I

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<100

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<200 IOOcm IS

-Piatfonn

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<100

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-Clean Area

<I

<I

-F

<100

<500*

<20

<200 lOOem INSTRUMENT USED PRM-7 CP-S R0-20 PNR-4 TBM-E-120 RM-14 RM-IS PAC*ISA LUDLUM*I2

,SERIAL NUMBER 285 1022 825

'An:a Posted: (c:in:le appllable) ~

HRA ~")l:i~ AIRBORNE PROBE a AC-JA. (U) 10%

X PROBE bg PANCAKE 20%

X COMMENTS

  • 43-4 (U) 10%

EFF.

EFF.

(4P (4P GEO.)

OEO.)

NEO 289 (REV. 07/10)

I SURVEYOR (print and sign)

!REVIEWER NO.

HITACHI Name and sigilatures on Original at GEH Vallecitos C-024 LOCATION DATE:

VALLECITOS NUCLEAR CENTER 09/13/18 NUCLEAR SAFETY SURVEY RECORD 200 Area GETR Containment (page 2 of2)

TIME:

1230 X

Rouline REASON o

Special Annual Survey ITEMS OR LOCATION DOSE RATE DIRECf READING SMEAR READINGS llem 11 a

~.!:

Pillaacc !:.

ba b&

ba No.

mRadlll mRib dPM

.UOM CPM dPM CPM.

dPM AREA I

3nl Floor-Zone Area Floor Drain 6

6 c

I 2 Elevator

<1

<1 F

<100

<SOO " <20

<200. 100cm2 J

Basement - Clean Area

<I

<I F

<100

<SOO

<20

<200 100cm 4

- Filter Bank

<1

<1 F

s

-Zone Area 3

3 F

<100

<SOO

<20

<200 lOOcm 6

- Control Rod Stora2e so so c

7

- Control Rod Repair Hood l.S 1.5 c

8

-Autoclave I Rad Work Area

<1

<1 c

9 Mezzanine between x-" & 3nt Floors

<1

<1 F

<100

<500

<20

<200 100cm 10 II 12 13 14 15 16 INSTRUMENT USED PRM-7 CP-S R0-20 PNR-4 TBM-E-120 RM-14 RM-15 PAC*ISA LUDLUM-12 SERIAL NUMBER 285 1022 825 Area Posted: (cin:lc applicable) (ID HRA ~

AIRBORNE PROBE a AC-JA (U) 10%

X PROBE bs PANCAKE 20%

X

~MMENTS EFF.

a 43-4 (U) 10%

EFF.

(4P (4P GEO,)

GEO.)

NEO 2119 (REV. 07/10)

ATTACHMENT 2:

Air Sample Data for Vallecitos Reactor Annual Inspection 2018 Initial lHourDecay

>24 Hour Decay Sample Alpha Beta Alpha Beta Alpha Beta Reactor Location Volumefmll ncpm uCI/ml ncpm uCI/ml ncpm ud/ml ncpm uCi/ml

!!9!!!!

uCI/ml ncum ud/ml VBWR First Floor 2.83E+06 1033.52 4.52E-10 2701.42 1.28E-09 132.54 5.80E-11 291.23 1.27E-10 0.10 4.37E-14 3.45 1.64E-12 Basement 2.83£+06 435.66 1.91E-10 1092.81 5.18E-10 102.95 4.SOE-11 235.53 1.03E-10 1.20 5.25E-13 4.02 1.91£-12 Fuel Pool 2.83£+06 365.41 1.60E-10 896.58 4.2SE-10 98.45 4.31£-11 209.25 9.15£-11 0.40 1.75E-13 6.21 2.94£-12 EVESR First Floor 2.83E+06 5773.13 2.53E*09 16093.67 7.63E-09 1164.69 5.10E-10 2344.94 1.03E-09 0.30 1.31E-13 1.33 6.30E*13 Basement 4.96E+06 9234.83 2.31E-09 22113.74 5.99E-09 692.30 1.73£-10 1402.02 3.51E-10 0.99 2.47E-13 48.15 1.30E-11 519' Level 2.83E+06 4054.53 1.77E-09 10074.52 4.78E-09 95.66 4.19E-11 190.97 8.35E-11 0.30 1.31E-13 10.63 5.04E-12 GETR First Floor 2.83E+06 749.67 3.28E-10 2013.23 9.54E-10 339.84 1.49E-10 759.32 3.32E-10 0.20 8.75E*14 1.44 6.83E*13 Basement 2.83E+06 495.53 2.17E-10. 1263.73 5.99E-10 41.38 1.81E-11 97.71 4.27E-11 1.30 5.69E*13 17.31 8.20E*12 Third Floor 2.83E+06 582.37 2.5SE*10 1524.15 7.22E-10 145.43 6.36E-11 309.95 1.36E-10 1.70 7.44E-13 10.36 4.91E-12 Tennelec System *A" Efffdency & Conversion Factors Alpha Effldency 36.36%

Beta Efficiency 33.56" dpm/uCI 2.22E+06 Alpha cpm/UCI 8.07E+OS Beta cpm/uCI 7.45E+OS Sampling Information Flaw Initial 1Hr Aggrox.

Mfoutes BIS!.

Total Total Samgle S.!f!!I!IL Sample Minutes Half-Ufe Be1ctor Location Date Samgled nme.On nmeOff S!!!l!l!led lmnl Row.(ft11 ml/ft1 Volume(mll nme

~ Decay lmtn.J VBWR First Ffoor 9/9/2018 9:40 10:00 20 5

100.0 28317 2.83E+06 10:10 12:00 110 37.1 VBWR Basement 9/13/2018 9:25 9:45 20 5*

100.0 28317 2.83E+06 I

10:05 11:20 75 36.0 VBWR Fuel Pool 9/13/2018 9:00 9:20 20 5

100.0 28317 2.83E+06 9:35 10:50 75 39.6 I

EVESR First Floor 9/9/2018 10:05 10:25 20 5

100.0 28317 2.83E+06 10:35 12:10 95 41.1 EVESR Basement 9/14/2018 10:40 11:15.

35 5

175.0 2831-7 4.96E+06 11:30 13:40 130 34.8 EVESR 519' Level 9/14/2018 10:10 10:30 20 5

100.0 28317 2.83E+06 10:50 13:50 180 33.3 GETR First Floor 9/9/2018 12:03 12:23 20 5

100.0 28317 2.83E+06 12:33 13:23 so 43.8 GETR Basement 9/13/2018 11:05 11:25 20 5

100.0 28317 2.83E+06 11:50 14:05 135 37.7 GETR Third Ffoor 9/13/2018 11:40 12:00 20 5

100.0 28317 2.83£+06 12:15 13:30 75 37.5