ML20155E101
| ML20155E101 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/06/1998 |
| From: | Zimmerman R NRC (Affiliation Not Assigned) |
| To: | ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20155E105 | List: |
| References | |
| NUDOCS 9811040187 | |
| Download: ML20155E101 (5) | |
Text
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7590-01-P UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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ENTERGY OPERATIONS, INC.
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Docket Nos. 50-313
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and 50-368
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(Arkansas Nuclear One, Units 1 and 2)
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EXEMPTION l.
I Entergy Operations, Inc., (the licensee) is the holder of Facility Operating License Noc.
1 DPR-51 and NPF-6, which authorize operation of Arkansas Nuclear Ono, Units 1 and 2. The i
l licenses provide, among other things, that the licensee is subject to all rules, regulations, and orders of the Commission now or hereafter in e*fect.
f The facility consists of two pressurized-water reactors at the licensee's site located in Pope County, Arkansas.
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Section 70.24 cf Title 10 of the CODE OF FEDERAL REGULATIONS, " Criticality
- a Accident Requirements," requires that each licensee authorized to possess special nuclear i
material (SNM) shall maintain a criticality accident monitoring system in each area where such material is handled, used, or stored. Subsections (a)(1) and (a)(2) of 10 CFR 70.24 specify E
detection and sensitivity requirements that these monitors must meet. Subsection (a)(1) also il.
specifies that all areas subject to criticality accident monitoring must be covered by two 5811040187 981006 a
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2 detectors. Subsection (a)(3) of 10 CFR 70.24 requires licensees to maintain emergency procedures for each area in which this licensed SNM is handled, used, or stored and provides that (1) the procedures ensure that all personnel withdraw to an area of safety upon the sounding of a criticality accident monitor alarm, (2) the procedures must include drills to i
familiarize personnel with the evacuation plan, and (3) the procedures designate responsible individuals for determining the cause of the alarm and placement of radiation survey instruments in accessible locations for use in such an emergency. Subsection (b)(1) of 10 CFR 70.24 requires licensees to have a means to identify quickly personnel who have received a dose of 10 rads or more. Subsection (b)(2) of 10 CFR 7C,.24 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, j
Paragraph (c) of 10 CFR 70.24 exempts Part 50 licensees from the requirements of paragraph (b) of 10 CFR 70.24 for SNM used or to be used in the reactor. Paragraph (d) of 10 CFR 70.24 states that any licensee who believes that there is good cause why he should be granted an l
exemption from all or part of 10 CFR 70.24 may apply to the Commission for such an exemption and shall specify the reasons for the relief repluested.
Ill.
The SNM that could be assembled into a critical mass at ANO-1 and ANO-2 is in the form of nuclear fuel; the quantity of SNM other than fuel that is stored on site in any given location is small enough to preclude achieving a critical mass. The Commission's technical staff has evaluated the possibility of an inadverient criticality of the nuclear fuel at ANO-1 and ANO-2, and has determined that it is extremely unlikely for such an accident to occur if the
3 licensee meets the following seven criteria:
1.
Only one new assembly is allowed out of a shipping cask or storage rack at one time.
2.
The k-effective does not exceed 0.95, at a 95% probability,95% confidence levelin the event that the fresh fuel storage racks are filled with fuel of the maximum permissible U-235 enrichment and flooded with pure water.
3.
If optimum moderation occurs at low r..
.erator density, then the k-effective does not exceed 0.98, at a 95% probability,95% confidence levelin the event that the fresh fuel storage racks are filled with fuel of the maximum permissible U-235 enrichment and flooded with a moderator at the density corresponding to optimum moderation.
4.
The k-effective does not exceed 0.95, at a 95% probability,95% confidence level in the even+ that the spent fuel storage racks are filled with fuel of the maximum permissible U-235 enrichment and flooded with pure water.
5.
The quantity of forms of special nuclear material, other than nuclear fuel, that are stored on site in any given area is less than the quantity necessary for a critical mass.
6.
Radiation monitors, as required by General Design Criterion 63, are provided in fuel storage and handling areas to detect excessive radiation levels and to initiate appropriate safety actions.
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The maximum nominal U-235 enrichment is limited to 5.0 weight percent.
By letter dated October 31,1997 ole licensee requested an exemption from 10 CFR 70.24. In this request the licensee addressed the seven criteria given above. The Commission's technical staff has reviewed the licensee's submittals and has determined that the applicable criteria are satisfied for ANO-1 and ANO-2. Therefore, the stafflias determined that it is extremely unlikely for an inadvertent criticality to occur in SNM handling or storage areas at ANO-1 and ANO-2.
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The purpose of the criticality monitre. ; mquired by 10 CFR 70.24 is to ensure that if a criticality were to occur during the handling of SNM, personnel would be alerted to that fact and would take appropriate action. The staff has determined that it is extremely unlikely that such an accident could occur; furthermore, the licensee has radiation monitors, as required by General Design Criterion 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 from the requirements of 10 CFR 70.24.
IV.
The Commission has determined that, pursuant to 10 CFR 70.14, this exemption is authorized by law, will not ence.nger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the Commission hereby grants Entergy Operations, Inc., an exemption from the requirements of 10 CFR 70.24 for ANO-1 and ANO-2.
l Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will have no significant impact on the environment (63 FR 51380).
This exemption is effective upon issuance, f
FOR THE NUCLEAR REGULATORY COMMISSION f
oy. Zim er an, Acting Director l
ice of Nu ar Reactor Regulation Dated at Rockville, Maryland, this 6th day of October 1998.
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DISTRIBUTION:
$5ectet Filad PDIV-1 r/f o
CHawes WReckley October 6e 1998 e
MEMORANDU TO:
Rules and Directives Branch Division of Administrative Services Office of Administration FROM:
Office of Nuclear Reactor Regulation
SUBJECT:
ENENGY OPERATIONSe INC. - ANKANSAS NUCLEAR ONEe UNITS 142 One signed original of the Federe/ Register Notice identified below is attached for your transmittal i.
to the Office of the Federal Register for publication. Additional conformed copies (fhe ) of the Notice are enclosed for your use.
Notice of Receipt of Application for Construction Permit (s) and Operating License (s).
t Notice of Receipt of Partial Application for Construction Permit (s) and Facility License (s):
Time for submission of Views on Antitrust matters.
-l Notice of Consideration of issuance of Amendment to Facility Operating License. (Call with 30-day insert date).
Notice of Receipt of Application for Facility License (s): Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of issuance of Facility License (s) and Notice of Opportunity for Hearing, Notice of Availability of NRC Draft / Final Environmental Statement.
Notice of Limited Work Authorization.
Notice of Availability of Safety Evaluation Report.
- Notice of issuance of Construction Permit (s).
Notice of lasuance of Facility Operating License (s) or Amendment (s).
1 Order.
Exemption.
Notice of Grariting Exemption.
Environmental Assessment.
Notice of Preparation of Environmental Assessment.
l Receipt of Petition for Director's Decision Under 10 CFR 2.206.
Issuance of Final Director's Decision Under 10 CFR 2.206.
Other:
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DOCKET NOs'. W313 and W368 Attachment (s):~ As stated'
Contact:
W. Neckley Telephone:
415-1324 DOCUMENT NAME: ARA 1278.EXE Ta receive a copy of this document, indicate in the box:
"C* = Copy without attachment / enclosure
- E" = Copy with attachment / enclosure
- N* = No copy OFFICE LA/PD4-1 l
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l NAME CHawes W
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DATE.
10/ 7 /98
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OFFICIAL RECORD COPY u
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