ML080920130

Boiling Water Reactor - Transmittal of Annual Report No. 43 for the Year 2007

ML080920130
Person / Time
Site:	Vallecitos Nuclear Center
Issue date:	03/28/2008
From:	Latonya Mahlahla GE-Hitachi Nuclear Energy Americas
To:	Document Control Desk, NRC/FSME
References
LLM-2008-08
Download: ML080920130 (5)

Text

GE Hitachi HITACHI Nuclear Energy LaTonya Mahlahla Vallecitos Nuclear Center 6705 Vallecitos Rd Sunol, CA 94586 USA U.S. Nuclear Regulatory Commission T 925 862 4360 F 910-341-2972 One White Flint North Latonya.mohlala@ge.com 11555 Rockville Pike Rockville, Maryland 20852-2738 Attn: Document Control Desk March 28, 2008

Subject:

Annual Report for VBWR, 2007

Reference:

License DPR-1, Docket 50-18

Enclosure:

Annual Report No. 43 Enclosed is the Annual Report No. 43 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, Date:

,ea7-r, ý .2008.03.28 11:39:30 -07'00' LaTonya L. Mahlahla Mgr., Regulatory Compliance & EHS cc: John Buckley (email)

LLM-2008-08 VBWR Annual Report 1.J!-~c

GE Hitachi Nuclear Energy 0 ', HITACHI Vallecitos Nuclear Center Sunol, California VALLECITOS BOILING WATER REACTOR (DEACTIVATED)

ANNUAL REPORT NO. 43 FOR THE YEAR 2007 LICENSE DPR-1 DOCKET 50-18 MARCH 2008

VBWR Annual Report No. 43 Vallecitos Boiling Water Reactor (Deactivated)

Annual Report No. 43 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, 2007 to December 31, 2007 is presented, as required by paragraph 5.d.2 of the license.

1.0

SUMMARY

VBWR - 2007 Component Removal Activities Component removal activities within the VBWR containment commenced during October 2007.

For disposal considerations, 2007 efforts focused primarily on the removal of components that were oversized and size-reduction was not practical. Specifically, the following items were removed and shipped for disposal in 2007:

• Large bore re-circ valves.

• Large electrical motor from re-circ pump

" Steam Generator

• Re-circ pumps

" Concrete floor plug

" Steam generator floor plugs

" Control Rod Drive Mechanism In order to remove the above items, additional materials (i.e. interferences) were also removed, including steam discharge lines, relief valve discharge lines, and miscellaneous conduit and structural steel. As of 12/31/07 a total of 4264 ft3 (168435 lbs) was removed and shipped for disposal as LSA waste. The water level within the reactor vessel was monitored and remained essentially constant throughout the report period.

Radiation levels remain essentially unchanged.

Page 1 of 3

VBWR Annual Report No. 43 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, with component removal activities ongoing.

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 VBWR was less than 1.2 E-2 mrem/year.

4.0 ACTIVITIES Routine inspections were conducted during this report period. Component removal activities started in October 2007 and are described in Section 1.0, Summary.

5.0 ORGANIZATION The organizational structure was unchanged during 2007. The Vallecitos Nuclear Center (VNC)

Site Manager was D. W. Turner. The VBWR Facility Manager was C. W. Bassett.

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 Page 2 of 3

VBWR Annual Report No. 43 C. W. Bassett, Manager Facilities Maintenance and QA Table 1 Radiation and Contamination Level Data Vallecitos Boiling Water Reactor (Deactivated)

Contamination Levels Surface Smears Airborne Radiation Levels Beta-Gamma* Beta-Gammat (mR/h Gamma) (cpm/ft 2 x 103) (p.Ci/cc x 1010)

Date of Measurement: 12/06 12/07 12/06 12/07 12/06 12/07 Reactor Enclosure, Main Floor General <1.0 <1.0 0.2 0.3 0.009 0.03 Top of Spent Fuel Pit Cover <1.0 <1.0 0.2 <0.1 0.009 0.04 Reactor Basement 0.009 0.04 Upper Level, Field <1.0 <1-1.5 ........

West Ladder, Bottom 1 5.5 0.3 0.4 ....

East Ladder, Bottom <1.0 <1.0 0.3 0.6 0.03 .03 Between Recirculation 3 2.5 ........

Pumps (located 2 feet above deck) (* RCPs 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.

For conversion to d/m, assume an instrument efficiency of 20%.

t 24-hour decayed values Page 3 of 3