ML120260674: Difference between revisions

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| document type = License-Operating (New/Renewal/Amendments) DKT 50
| document type = License-Operating (New/Renewal/Amendments) DKT 50
| page count = 1
| page count = 1
| project = TAC:L24561
| stage = Approval
}}
}}



Latest revision as of 23:16, 5 December 2019

Enclosure 1a: Yaeca a 159 License Page 3 (R. Mitchell Letter Yankee Atomic Electric Company - Issuance of Amendment to the Operating License No. DPR-3 Regarding the Physical Security Plant (TAC No. L24561))
ML120260674
Person / Time
Site: Yankee Rowe
Issue date: 01/24/2012
From:
NRC/NMSS/SFST/LID/LB
To: Recasha Mitchell
Yankee Atomic Electric Co
Goshen J, NMSS/SFST 492-3325
Shared Package
ML120260656 List:
References
TAC L24561
Download: ML120260674 (1)


Text

and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level Amendment #142 The licensee is not authorized to operate the reactor. Fuel may not be placed 8/5/1992 in the reactor vessel.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment #145 Amendment No. 157, are hereby incorporated in the License. The licensee 9/4/1992 shall possess and maintain the facility in accordance with the Technical Specifications.

(3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Amendment #156 Commission-approved physical security, guard training and qualification, and 3/12/2002 safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revision to 10 CFR 73.55 (51 FR 27817 and 17822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plan, which contains Safeguards Amendment #159 Information protected under 10 CFR 73.21, is entitled, Physical Security Plan 1/24/2012 for Yankee Rowe Independent Spent Fuel Storage Installation. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

(4) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Amendment #144 Report for the facility and as approved by NRC Safety Evaluation Reports 8/20/1992 dated March 15, 1979, and as supplemented October 1, 1980, and August 27, 1986, subject to the following provisions:

The licensee may make changes to the approved Fire Protection Program without prior NRC approval if these changes do not reduce the effectiveness of Amendment #157 fire protection for facilities, systems, and equipment which could result in a 4/17/2003 radiological hazard, taking into account the decommissioning plant conditions and activities.