ML20236R200
| ML20236R200 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/15/1998 |
| From: | Collins S NRC (Affiliation Not Assigned) |
| To: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML20236R202 | List: |
| References | |
| NUDOCS 9807210295 | |
| Download: ML20236R200 (3) | |
Text
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7590-01-P 4
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ljNIIELhTATES OF AMERICA NUCLEAR REGULATORY COMMISSION in the Matter of
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VIRGINIA ELECTRIC AND POWER
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Docket Nos. 50 280 and S0-281 COMPANY
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Surry Power Station, Units 1 and 2
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1 EXEMPTION i.
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The Virginia Electric and Power Company (VEPCO, the licensee) is the holder of Facility Operating License No. DPR-32 and Facility Operating License No. DPR-37, which authorize operation of the Surry Power Stahon, Units 1 and 2. The licenses provide that the licensee is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC or
' the Commission) now or hereafter in effect.
The facility consists of two pressurized-water reactors at the licensee's site located in Surry County, Virginia.
II.
Title 10 of the code of Federal Regulations (10 CFR) Section 70.24, " Criticality Accident Requirements," requires that each bconsee authorir-A to possess special nuclear material shell maintain a criticality accident monitoring system in each area in which such material is handled, used, or stored. Sections 70.24 (a)(1) and (a)(2) specify detection and sensitivity requirements that these monitors must meet. Section 70.24(a)(1) also specifies that all areas subject to crthcality accident monitoring must be covered by two detectors. Section 70.24(a)(3) requires licensees to maintain emergency procedures for each area ire which this licensed special i
kDOC 80 P
2 nuclear material is handled, used, or stored, and gees (1) that the procedures ensure that all personnel withdraw to r.n area of safety upon the sounding of a cribcality accident monitor alarm, (2) that the procedures must include drills to familiarize personnel with the evacuation plan, and (3) that the procedures designate responsible individuals for determining the cause of the alarm and placement of radiation survey instruments in socessible locations for use in such an emergency. Section 70.24(b)(1) requires licensees to have a means by wh!ch to quicidy identify personnel who have received a dose of 10 rods or more. Section 70.24(b)(2) requires licensees to maintain personnel decontamination facilities, to maintain arrangements for a physician and other medical personnel qualified to handle radiation emergencies, and to maintain arrangements for the transportation of contaminated individuals to treatment facilities outside the site boundary. Section 70.24(c) exempts Part 50 licensees from the requirements of 10 CFR 70.24(c) for special nuclear material used or to be used in the reactor. Subsection 70.24(d) states that any licensee who believes that there is good cause why he should be j
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granted an exemption from all or part of 10 CFR 70.24 may apply to the Commission for such an exemptiu and shall specify the reasons for the relief requested.
Ill.
On August 21,19g7, the NRC granted an exemption from the requirements of 10 CFR 70.24 reflecting the licensee's use of fuel enriched to 4.1 weight percent U235. By letter dated l
Janusy 14,1908, VEPCO requested a revised exemption from 10 CFR 70.24(a) based on the use of fuel enriched to 4.3 weight percent U225 The Commission has reviewed the licensee's submittal and has determined that inadvertent crlhcality is not liksly to occur in special nuclear materials handing or storage areas at Suny Power Station, Units 1 and 2. The quantity of special nuclear material other than fuel that is stored on site is small enough to preclude achieving a critical mass.
3 The purpose of the criticality monitors required by 10 CFR 70.24 is to ensure that if a criticality were to occur during the handling of special nuclear material, personnel would be alerted to that fact and would take appropriate action. Although the staff has determined that such an accident is not likely to occur, the licensee has radiation monitors, as required by General Design Criteria 63, in fuel storage and handling areas. These monitors will alert personnel to excessive radiation levels and allow them to initiate appropriate safety actions.
The low probability of an inadvertent criticality together with the licensee's adherence to General Design Criterion 63 constitute good cause for granting an exemption to the requirements of 10 CFR 70.24(a).
IV.
The Commission has determined that, pursuant to 10 CFR 70.14, this exemption as revised is authorized by law, will not endanger life or property or the common defense and security, and !s otherwise in the public interest; therefore, the Commission hereby grants the following revised exsmption:
The Virginia Electric and Power Company is exempt from the requirements of 10 CFR 70.24(a) for the Surry Nuclear Power Station, Unit 1 and Unit 2.
Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this revised exemption will have no significant impact on the quality of the human environment (63 FR 38196
).
This revised exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 8
Office of Nuclear Reactor Regulation i
Dated at Rockville, Maryland this 15th day of July 1998.