ML100900467: Difference between revisions

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==SUMMARY==
==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 remained essentially constant throughout the report period.Radiation levels remain essentially unchanged.
All reactor systems have been removed from the containment except for the reactor vessel.The water level within the reactor vessel was monitored and remained essentially constant throughout the report period.Radiation levels remain essentially unchanged.
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 Table 1. The radiation/contamination levels listed are representative but not necessarily maximum values.Dismantling operations did not significantly increase the site's airborne radiological effluent release rate. Continuous general air sampling was performed within the VBWR containment during dismantling operations for personnel monitoring and to assess the potential release of radiological effluents to the environment.
===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 Table 1. The radiation/contamination levels listed are representative but not necessarily maximum values.Dismantling operations did not significantly increase the site's airborne radiological effluent release rate. Continuous general air sampling was performed within the VBWR containment during dismantling operations for personnel monitoring and to assess the potential release of radiological effluents to the environment.
Using The Comply Computer Code, a conservative estimate of the Effective Dose Equivalent to the public from all on site sources was less than 0.8 mrem/year.
Using The Comply Computer Code, a conservative estimate of the Effective Dose Equivalent to the public from all on site sources was less than 0.8 mrem/year.
Page 1 of 3 VBWR Annual Report No. 45 Table 1 Radiation and Contamination Level Data Vallecitos Boiling Water Reactor (Deactivated)
Page 1 of 3 VBWR Annual Report No. 45 Table 1 Radiation and Contamination Level Data Vallecitos Boiling Water Reactor (Deactivated)

Revision as of 06:08, 14 October 2018

Submittal of Annual Report No. 45 for Deactivated Vallecitos Boiling Water Reactor for 2009
ML100900467
Person / Time
Site: Vallecitos Nuclear Center
Issue date: 03/30/2010
From: Turner D W
GE-Hitachi Nuclear Energy Americas
To:
Document Control Desk, NRC/FSME
References
Download: ML100900467 (4)
v • d • e


Text

HITACHI GE Hitachi Nuclear Energy David W. Turner Manager, Vallecitos Nuclear Center 6705 Vallecitos Rd Sunol, CA 94586 USA U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Attn: Document Control Desk T 925 862 4344 F 910 341 2577 davidw.turner@ge.com March 30th, 2010

Subject:

Reference:

Enclosure:

Annual Report for VBWR, 2009 License DRP-1, Docket 50-18 Annual Report No. 45 Enclosed is the Annual Report No. 45 for the deactivated Vallecitos Boiling Water Reactor (VBWR) located at Vallecitos Nuclear Center near Sunol, California.

If there are any questions or additional information required, please contact me at the number above.Sincerely Yours, Digitally signed by David W. Turner Date: 2010.03.30 13:24:24-07'00'David W. Turner Manager, Vallecitos Nuclear Center cc: John Buckley, NRC (by e-mail)Robert Evans, Region IV (by e-mail)Ob ý' 6 GE-Hitachi Nuclear Energy Americas, LLC 0 HITACHI GE Hitachi Nuclear Energy Vallecitas Nuclear Center Sunol, California VALLECITOS BOILING WATER REACTOR (DEACTIVATED).

ANNUAL REPORT NO. 45 FOR THE YEAR 2009 LICENSE DPR-1 DOCKET 50-18 MARCH 2010 VBWR Annual Report No. 45 Vallecitos Boiling Water Reactor (Deactivated)

Annual Report No. 45 GE Hitachi Nuclear Energy has maintained the Vallecitos Boiling Water Reactor (VBWR) in a deactivated status under the authority of Amendment No. 19 to License DPR-1, Docket 50-18. In this annual report, a summary of the status of the facility for the period of January 1, 2009 to December 31, 2009 is presented, as required by paragraph 5.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 remained essentially constant throughout the report period.Radiation levels remain essentially unchanged.

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 Table 1. The radiation/contamination levels listed are representative but not necessarily maximum values.Dismantling operations did not significantly increase the site's airborne radiological effluent release rate. Continuous general air sampling was performed within the VBWR containment during dismantling operations for personnel monitoring and to assess the potential release of radiological effluents to the environment.

Using The Comply Computer Code, a conservative estimate of the Effective Dose Equivalent to the public from all on site sources was less than 0.8 mrem/year.

Page 1 of 3 VBWR Annual Report No. 45 Table 1 Radiation and Contamination Level Data Vallecitos Boiling Water Reactor (Deactivated)

Contamination Levels Surface Smears Airborne Radiation Levels Beta-Gamma Beta-Gamma*(mR/h Gamma) (dpm/ft 2) (R+/-Ci/cc x 10-10)Date of Measurement:

12/08 12/09 12/08 12/09 12/08 12/09 Reactor Enclosure, Main Floor 0.02 11.4 General <1.0 <1.0 750 2,500 Top of Spent Fuel Pit Cover <1.0 1.0 1,000 1,000 Reactor Basement 0.02 4.69 Upper Level <1.0 <1.0 -- 1,000 West Ladder, Bottom 5.0 <1.0 11,000 4,000 East Ladder, Bottom <1.0 <1.0 10,000 10,000 Between Recirculation Pumps (located 2 feet above deck) (* RCPs <1.0 <1.0 -removed)Note: Radiation levels, surface smears, and air samples may vary from survey to survey as they are taken in general areas rather than at specific locations.

24-hour decayed values Page 3 of 3

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