ML14196A426

Draft Supplemental Information Required for Review of Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation License Amendment Request for BVPS-2

ML14196A426
Person / Time
Site:	Beaver Valley
Issue date:	07/15/2014
From:	Jeffrey Whited Plant Licensing Branch 1
To:	FirstEnergy Nuclear Operating Co
References
Download: ML14196A426 (2)

Text

DRAFT SUPPLEMENTAL INFORMATION NEEDED REVISED TECHNICAL SPECIFICATION 4.3.2, SPENT FUEL STORAGE POOL MINIMUM INADVERTENT DRAINAGE ELEVATION FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT 2 DOCKET NO. 50-412 The Nuclear Regulatory Commission (NRC) staff has reviewed the application submitted by FirstEnergy Nuclear Operating Company (FENOC, the licensee) to amendment the operating license for Beaver Valley Power Station, Unit No. 2 (BVPS-2) by letter dated June 2, 2014,1 and concluded that the information delineated below is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment.

Pursuant to the Code of Federal Regulations (10 CFR) Part 50.90, whenever a holder of an operating license desires to amend the license, application for the amendment must be filed with the Commission, as specified in 10 CFR 50.4(b)(1), as applicable, fully describing the changes desired, and following as far as applicable, the form prescribed for original applications.

In the enclosure to the letter dated June 2, 2014, FENOC, submitted an evaluation which supports the request to change Technical Specification (TS) 4.3.2, Drainage. Specifically, TS 4.3.2 requires that the spent fuel storage pool be designed to prevent inadvertent draining of the pool below a certain specified elevation. The proposed change would revise this specified elevation in TS 4.3.2 to reflect the actual installed piping by lowering the elevation by 5 inches.

The licensee discusses how the amendment request meets the five design provisions listed in General Design Criterion (GDC) 61, Fuel storage and handling and radioactivity control, set forth in Appendix A, General Design Criteria for Nuclear Power Plants, of 10 CFR 50. These provisions require that fuel storage and handling, radioactive waste, and other systems that may contain radioactivity be designed to assure adequate safety under normal and postulated accident conditions. However, it is unclear how provision two of General Design Criterion 61 is met to ensure that suitable shielding for radiation protection is available with the given information.

GDC 61 states, in part, that:

The fuel storage and handling, radioactive waste, and other systems which may contain radioactivity shall be designed to assure adequate safety under normal and postulated accident conditions. These systems shall be designed 1

Agencywide Documents Access and Management System Accession No. ML14153A399.

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(2) with suitable shielding for radiation protection Page 4 of the attachment states, in reference to GDC 61 (2), in part, that:

This design provision directly relates to the proposed [TS] change. A discussion of the effects of the proposed [TS] change on radiation shielding is provided later in this Technical Evaluation.

Page 5 of the attachment states, in part, that:

The conservatively high calculated gamma radiation dose rate for personnel located at the fuel building operating floor elevation, directly above freshly discharged fuel assemblies stored in the spent fuel storage pool with the pool water level reduced to the 750 feet, 10 inch elevation (providing at least 9.84 feet of water above the active fuel) is estimated to be approximately 280 millirem per hour. This calculated result can be used to estimate operator exposure for post drain-down event mitigation activities.

Page 6 of the attachment states, in part, that:

Reducing the spent fuel storage pool minimum shielding depth from the UFSAR specified 10 feet above the top of the fuel stored in the racks to 9.84 feet above the top of the active fuel stored in the racks corresponds to an approximate 51 millirem per hour increase in the radiation dose rate for personnel located at the fuel building operating floor elevation It is unclear to the NRC staff the basis of these statements which discusses the estimated gamma radiation dose rate for personnel located at the fuel building operating floor elevation, directly above freshly discharged fuel assemblies stored in the spent fuel storage pool with the pool water level reduced to the 750 feet, 10 inch elevation to be approximately 280 millirem per hour since no calculation sheet is provided. In order to make the application complete, the NRC staff requests that FENOC supplement the application with:

1) A calculation sheet which cites the appropriate Regulatory Guide methodology and provides the calculation that demonstrates an estimated dose rate of approximately 280 millirem per hour for a person located at the fuel building operating floor elevation, directly above freshly discharged fuel assemblies stored in the spent fuel storage pool with the pool water level reduced to the 750 feet, 10 inch elevation.

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