ML20214P672
| ML20214P672 | |
| Person / Time | |
|---|---|
| Site: | Battelle Memorial Institute, 07000008 |
| Issue date: | 07/19/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214P605 | List: |
| References | |
| NUDOCS 8706030485 | |
| Download: ML20214P672 (3) | |
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SAFETY EVALUATION BY TH2 0FFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT No.13 TO LICENSE NO. R-4 BATTELLE MEMORIAL INSTITUTE DOCKET NO. 50-6 Introduction On March 4, 1976, Battelle Memorial Institute (the licencee) submitted an application for license amendment to change the Technical Specifications for the Battelle Research Reactor (BRR). The proposed changes delete the operability and surveillance requirements for equipment no longer ne eded -
T and subsequently removed following decommissioning. In addition, a revised facility description and r,evised reporting requirements have been incorporated in the proposed Technical Specifications.
In the process of reviewing the application for license amendment dated March 4, 1976, it was determined that changes in the proposed Technical Specifications would be needed in order to meet our requirements. The -
changes in the proposed Technical Spec.ifications were made with the concurrence of the licensee.
Discussion On March 10, 1975 we issued Lictnse Amendment No. 10 for the BRR which authorized the licensee to possess but not operate the BRR. Sutsequently, on March 19, 1975 we issued .sut Order Authorizing Dismantling of the BRR.
The Cffice of Inspection and Enforcement (OIE) Report No. 50-006/75-03, dated October 23, 1975, indicates that the licensee con.pleted decommissioning of the BRR on September 17, 1975. The OIE report of October 23, 1975 furthur indicated that (1) all spent fuel and radioactive waste had been removed from the facility, (2) residual radiation exceeding SmR/hr does not exist in any facility areas that are not physically secured, and (3) smear survey results show that surface contamination is below the guidelines for decommissioned facilities as set forth in Regulatory Guide 1.86. This information, together with the Technical Specifications issued with License Amendment No. 10 which provided administrative and procedural controls during and following decommissioning, indicates that the licensee can retain the BRR facility, in its present condition, indefinitely. However, the licensee has proposed that certain Technical Specifications be changed in order to simplify the administration of the facility under the "Pocsession Only" License. Accordingly, the licensee has proposed deletion of those Technical Specifications which address the operability and surveillance requirements for (1) monitors of radiation, criticality, and water level, and (2) the reactor confinement area. In addition, the 8706030485 870514 ' .
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< licensee has proposed to amend the description of the design feature of the decommissioned facility, contained in the Technical Specifications, to reflect the revised status of the facility. i As part of our review, we have proposed, and the licensee has concurred, ;
1 that the reporting requirements in the Technical Specifications be revised
. to reflect the guidance of Regulatory Guide 1.16, Revision 4.
Evaluation !
Our evaluation of the proposed Technical Specification changes are contained in the following sections.
- 1. Deletion of Operability and Surveillance Requirements for (a) Radiation.
Criticality, and Water Level Monitors, and (b) the Reactor Confinement
. Area.
Technical S t y.cifications 3.1 and 4.1 provided operability and surveillance requirements for the reactor pool level and criticality monitors until all fuel was shipped off-site. The site inspection .
report dated October 23, 1975 confirmed that all fuel was shipped offsite. Morecver, by License Amendment No. 12 dated November 26, 1975, we deleted the licensee's authorization to possess reactor fuel in connection with possession of the BRR; therefore, reactor fuel cannot i be reintroduced at the BRR facility. Accordingly, it is appropriate that Technical Specifications 3.1 and 4.1 be deleted.
Technical Specifications 3.3 and 4.3 provide operability and surveillance i requirements for airborne-radiation monitors. These monitors were required during decommissioning to detect' airborne contamination
- resulting from demolition and other decommissioning activities. In
! addition, Technical Specifications 3.4 and 4.4 required the establishment
- and maintenance of a " confinement area" to minimize the release of f
airborne contamination in the event that such contamination occurred.
> The Inspection Report dated October 23, 1975 indicates that all
- decommissioning activities have been completed. The remaining radioactivity, i
other than an acceptable level of surface contamination, is entrained
'in the facility structures and cannot become airborne. Quarterly facility radiation surveys will continue to assure that the existing contamination will remain entrained. Accordingly, it is appropriate that Technical i Specifications 3.3, 3.4, 4.3, and 4.4 be deleted.
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- 2. Revised Description of the Design Features of the BRR l
Technical Specification 5.3, entitled "ruel Storage", requires fuel to be stored such that the geometric array ensures suberiticality and
! adequate cooling is provided. Since no fuel is located in the BRR,
.nor can any be reintroduced, no requirements on fuel storage need be in j - t ,
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