ML083020128

EVESR Amendment 7, Safety Evaluation Report

ML083020128
Person / Time
Site:	Vallecitos File:GEH Hitachi icon.png
Issue date:	12/01/2008
From:	Buckley J NRC/FSME/DWMEP/DURLD/RDB
To:
Buckley, J TNRC/DWMEP, 415-6607
Shared Package
ML083020133	List: ML083020118 ML083020120 ML083020128
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Download: ML083020128 (4)

Text

SAFETY EVALUATION OFFICE OF FEDERAL AND STATE MATERIALS &

ENVIRONMENTAL PROTECTION PROGRAMS AMENDMENT NO. 7 TO FACILITY OPERATING LICENSE NO. DR-10 GE-HITACHI ESADA VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR (EVESR)

DOCKET NO. 50-183

1.0 INTRODUCTION

General Electric (GE)-Hitachis license amendment request dated June 23, 2008 (ADAMS No.

ML081780099), with supplements dated August 11, 2008 (ML082260044), August 19, 2008 (ML082350078), and October 9, 2008 (ML082840704), requested that the following general changes be made to the Technical Specifications (TSs):

• expand the scope of principal activities that can be conducted under the license; and

• remove unnecessary access control and locking requirements to areas below the 549-ft elevation of the EVESR containment, and control access to all areas within the EVESR containment in accordance with 10 CFR 20.1601.

2.0 BACKGROUND

The EVESR was a light water moderated, steam cooled, superheat reactor which used slightly enriched uranium dioxide as fuel. Its purpose was to provide information on the suitability of various types of experimental superheat fuel elements. The EVESR operated at a maximum power level of 17 megawatts thermal. The reactor was shut down on February 1, 1967, and all of the fuel and other special nuclear material transferred from the facility. In October 1967, GE requested that the EVESR license be terminated. The EVESR license was amended on April 15, 1970, to authorize possession but not operation of the reactor.

License DR-10 authorizes GE-Hitachi to dismantle components above the 549-ft elevation from the EVESR facility in accordance with the provisions of 10 CFR Part 20. GE-Hitachi plans to remove piping, pumps, valves, control systems, walkways and some non-structural shielding below the 549-ft elevation as part of the Vallecitos Nuclear Center liabilities Reduction Project.

GE-Hitachi has no plans, and is not requesting authorization, to remove the reactor vessel or the biological shield.

Enclosure 2

2 3.0 EVALUATION In order to effectively conduct the work under the Vallecitos Nuclear Center liabilities Reduction Project, GE-Hitachi is proposing to revise the TSs to: (1) expand the scope of activities allowed under its license to include the removal of components below the 549-ft elevation level; and (2) revise the radiological control requirements for areas below the 549-ft elevation. GE-Hitachi is proposing two changes to the TSs. Each of the proposed changes is evaluated below.

3.1 Proposed Change 1 Section A.2 of the TSs currently states:

The principal activities carried on within the plant area shall be the possession of the reactor facility, the dismantling of components other than the reactor pressure vessel and activities authorized by licenses issued by appropriate regulatory authorities, provided such activities do not involve access, except for reason of inspection, maintenance and surveillance, to areas below the 549-ft. elevation within the containment building.

GE-Hitachi is proposing to delete the text in bold above such that the revised Section A.2 will read:

The principal activities carried on within the plant area shall be the possession of the reactor facility, the dismantling of components other than the reactor pressure vessel and activities authorized by licenses issued by appropriate regulatory authorities.

License No. DR-10 currently allows GE-Hitachi to dismantle components in the containment building above the 549-ft elevation level. GE-Hitachis proposed revision of TS A.2 will expand what is allowed under the license to include the dismantlement of components below the 549-ft elevation level. The requirement restricting access to areas below 549-ft. elevation in the containment building was added to TS Sections A.2 and C.3 in Amendment No. 1, in June 1968. In 1968, GE planned to use the deck of the 549-ft elevation area as a platform to conduct tests and experiments. The purpose for adding the specific access controls for areas below 549-ft. elevation in the containment building was to restrict access to highly radioactive areas during the conduct of these tests and experiments. At the time, radiation levels were measured at 1 mr/hr on the 549-ft level deck with elevated radiation levels at locations below the 549-ft level throughout the other containment levels (e.g. 30 mr/hr at the top of the spent fuel pool and 65 mr/hr at a pipe location on the 503-ft level).

Since 1968 the radiation levels below the 549-ft elevation have been reduced and stabilized.

Measurements taken in 2008 in the EVESR containment indicate that, with the exception of one elevated area of the 519-ft level, all direct readings are less than 1 mr/hr. Since GE no longer conducts tests and experiments on the 549-ft deck and the radiation levels have essentially dropped below 1 mr/hr, the factors which resulted in restricting access to the 549-ft elevation, no longer exist. GE-Hitachi has no plans, and is not requesting authorization to remove the reactor vessel or the biological shield, therefore, component removal below the 549-ft level will not increase the probability or consequences of an accident previously evaluated.

3 3.2 Proposed Change 2 Section C.3 of the TSs currently states:

Access to areas below the 549-ft. level shall remain covered by concrete blocks over the reactor vessel and the head and shield plug storage pit, by a wood cover over the empty spent fuel storage pool and by locked covers on the personnel and equipment access hatchways.

Keys to locks on the hatches and on the crane power switch shall be available only to the facility supervisor or his designated alternate.

GE-Hitachi is proposing to delete the text in Section A.2 and replace with the following text:

Access to areas of the EVESR containment shall be controlled in a manner consistent with the requirements of 10 CFR 20.1601, Control of access to high radiation areas, as applicable.

The access controls for areas below 549-ft. elevation in the containment building were added to TS Sections A.2 and C.3 in Amendment No. 1, in June 1968. In 1968 GE planned to use the deck of the 549-ft elevation area as a platform to conduct tests and experiments. The purpose for adding the specific access controls for areas below 549-ft. elevation in the containment building was to prevent personnel conducting tests and experiments from accessing the areas below the 549-ft level while maintaining the 549-ft deck as a work area. At the time, radiation levels were measured at 1 mr/hr on the 549-ft level deck with elevated radiation levels at locations below the 549-ft level throughout the other containment levels (e.g. 30 mr/hr at the top of the spent fuel pool and 65 mr/hr at a pipe location on the 503-ft level).

Since 1968 the radiation levels below the 549-ft elevation have been reduced and stabilized.

Measurements taken in the EVESR containment in 2008 indicate that, with the exception of one elevated area of the 519-ft level, all direct readings are less than 1 mr/hr. GE-Hitachi no longer conducts tests and experiments on the 549-ft deck. Only personnel involved in monitoring or component removal are granted access to the EVESR containment, so the placement of shield blocks is no longer necessary. Further, radiation levels below the 549-ft level have essentially dropped below 1 mr/hr. Therefore, the factors which resulted in restricting access to the 549-ft elevation, no longer exist.

Given that the radiation levels below the 549-ft level have significantly decreased, and personnel are no longer conducting tests and experiments on the 549-ft deck, GE-Hitachis proposal to control all areas in the EVESR containment in accordance with 10 CFR Part 20, will not increase the probability or consequences of an accident previously evaluated.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the State of California was consulted regarding the proposed issuance of the amendment. Copies of the draft license amendment and SER were provided to the State for information and comment. The State had no comments.

4

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to the use of facility components located within the restricted area as defined in 10 CFR Part 20. Further, the amendment: (1) will result in no significant hazards; (2) will result in no significant increase in the types or significant increase in the amounts of any effluents that may be released offsite; and (3) will result in no significant increase in the individual or cumulative occupational radiation exposure. The amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: John T. Buckley Date: December 1, 2008