ML042390481

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Biweekly Notice Memo, Notice of Consideration, Revise Technical Specifications to Reflect Removal of All Spent Nuclear Fuel from HNP Spent Fuel Pool, & Delete Requirement for Submittal of Annual Occupational Radiation Exposure Report
ML042390481
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 09/09/2004
From: Tanya Smith
NRC/NMSS/DWMEP/DD
To:
NRC/NRR/DLPM
References
-RFPFR, FOIA/PA-2005-0203, TAC L60567
Download: ML042390481 (4)


Text

September 9, 2004 MEMORANDUM TO: Biweekly Notice Coordinator FROM: Theodore B. Smith, Project Manager /RA/

Reactor Decommissioning Section Decommissioning Directorate Division of Waste Management and Environmental Protection Office of Nuclear Material Safety and Safeguards

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. L60567)

Connecticut Yankee Atomic Power Company, Docket No. 50-213, Haddam Neck Plant, Middlesex County, Connecticut Date of amendment request: August 11, 2004 Description of amendment requests:

The Haddam Neck Plant (HNP) is currently undergoing active decommissioning. The proposed amendment would revise Technical Specifications (TS) to reflect removal of all Spent Nuclear Fuel (SNF) from the HNP spent fuel pool, and delete the requirement for submittal of an annual Occupational Radiation Exposure Report consistent with Industrys Technical Specifications Task Force (TSTF)-369, Revision 1.

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:

In accordance with 10 CFR 50.92, CYAPCO has reviewed the proposed changes and concluded that the proposed changes do not involve a Significant Hazard Consideration (SHC).

The following is provided in support of this conclusion:

Incorporation of TSTF-369, Revision 1 CYAPCO has reviewed the no significant hazards consideration determination published in the Federal Register (69FR35067) as part of the CLIIP. CYAPCO has concluded that the determination presented in the Federal Register is applicable to the HNP and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91.

Deletion and Relocation of Technical Specifications The proposed changes do not involve an SHC because the changes would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed changes (deletion of operational requirements and certain design requirements) reflect the complete transfer of the spent fuel from the spent fuel pool to the Independent Spent Fuel Storage Installation (ISFSI). Design basis accidents related to the spent fuel pool are discussed in the Haddam Neck Plant (HNP) Updated Final Safety Analysis (UFSAR) Chapter

15. These postulated accidents are predicated on spent fuel being stored in the spent fuel pool.

With the removal of the spent fuel from the spent fuel pool, there are no remaining safety related Structures, Systems, and Components (SSCs) to be monitored and there are no credible accidents that require the actions of a Certified Fuel Handler or an Equipment Operator to prevent occurrence or mitigate the consequences of an accident.

In addition, the HNP UFSAR Chapter 15 also provides a discussion of other radiological events postulated to occur as a result of decommissioning with the bounding consequences resulting from a fire in a resin container. The proposed changes do not have an adverse impact on decommissioning activities or any of their postulated consequences.

The proposed changes related to the relocation of certain administrative requirements do not affect operating procedures or administrative controls that have the function of preventing or mitigating any design basis accidents. In addition, these proposed changes are consistent with the guidance of NRC Administrative Letter 95-06.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of any accident previously evaluated.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes eliminate the operational requirements and certain design requirements associated with the storage of the spent fuel in the spent fuel pool, and relocate certain administrative controls to the Connecticut Yankee Quality Assurance Program (CYQAP). With the complete removal of the spent fuel from the spent fuel pool, there are no safety related SSCs that remain at the plant. Thus the proposed changes will not have any effect on the operation or design function of safety related SSCs. The proposed changes do not introduce any new failure modes. Therefore, the proposed changes will not create the possibility of a new or different kind of accident from any previously evaluated.

3. Involve a significant reduction in a margin of safety.

The design basis and accident assumptions within the HNP UFSAR and the Technical Specifications relating to spent fuel are no longer applicable. The proposed changes do not affect remaining plant operations, systems, or components supporting decommissioning activities. In addition, the proposed changes do not result in a change in initial conditions, system response time, or in any other parameter affecting the course of a decommissioning

activity accident analysis. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.

NRC Section Chief: Claudia Craig

activity accident analysis. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.

NRC Section Chief: Claudia Craig DISTRIBUTION:

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