ML053120400

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Biweekly Notice Memo, Notice of Consideration, Proposes to Relocate the License Condition Associated with the Shutdown Cooling Open Permissive Interlock to the Technical Requirements Manual
ML053120400
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 11/17/2005
From: Holland D
Plant Licensing Branch III-2
To:
Plant Licensing Branch III-2
Holland D, NRR/DLPM, 415-1436
References
TAC MC7540
Download: ML053120400 (4)


Text

November 17, 2005 MEMORANDUM TO: Biweekly Notice Coordinator FROM: Drew G. Holland, Project Manager /RA Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE -

NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (TAC NO. MC7540)

Entergy Operations, Inc., Docket No. 50-368, Arkansas Nuclear One, Unit No. 2, Pope County, Arkansas Date of amendment request: June 29, 2005 Description of amendment request: Entergy Operations, Incorporated (Entergy) proposes to relocate the License Condition associated with the Shutdown Cooling (SDC) Open Permissive Interlock (OPI) to the Technical Requirements Manual (TRM). The Nuclear Regulatory Commission (NRC) approved Standard Technical Specifications, Combustion Engineering Plants (NUREG-1432) include a surveillance requirement for this function due to the complexity and differences of plant designs, which would not support complete removal of the function from the NUREG. For Arkansas Nuclear One, Unit 2 (ANO-2),

however, the OPI is not an assumed function that supports the accident analysis and does not meet the criteria in Section 50.36 of Title 10 of the Code of Federal Regulations (10 CFR) for inclusion in the technical specifications.

Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:

Biweekly Notice Coordinator

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The OPI function is not required to ensure continued safe operation of the ANO-2 facility. The OPI function is not considered an accident precursor or relied upon as a means of accident mitigation. The proposed change has no affect on plant design or operation.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The relocation of the OPI function to the TRM does not require any physical alteration to the plant or alter plant design. The OPI function is not considered an accident initiator nor is this function credited in any safety analyses for the prevention or mitigation of any accident.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The OPI function is not credited in a margin of safety analysis for any accident previously evaluated. Relocation of the OPI function requirements will not result in a credible increase in nuclear safety risk. Appropriate alarm, design features, and administrative controls continue to ensure proper isolation of the SDC system during plant operations with elevated RCS

[reactor cooling system] pressures. In addition, the OPI function will be relocated to the TRM, which is part of the Safety Analysis Report (SAR) and controlled by 10 CFR 50.59.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC

Biweekly Notice Coordinator staff proposes to determine that the amendment request involves no significant hazards consideration.

Attorney for licensee: Nicholas S. Reynolds, Esquire, Winston and Strawn, 1700 K Street, N.W., Washington, DC 20006-3817 NRC Branch Chief: David Terao

ML053120400 OFFICE LPLIV/PM LPLIV/LA LPLIV/BC NAME DHolland LFeizollahi DTerao for DJohnson DATE 11/16/05 11/14/05 11/17/05