[Federal Register Volume 62, Number 56 (Monday, March 24, 1997)]
[Notices]
[Page 13899]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-7337]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-213]
Connecticut Yankee Atomic Power Company; Haddam Neck Plant,
Notice of Withdrawal of Application for Amendment to Facility Operating
License
The U.S. Nuclear Regulatory Commission (the Commission) has granted
the request of Connecticut Yankee Atomic Power Company (the licensee)
to withdraw 18 proposed license amendments to Facility Operating
License No. DPR-61 for the Haddam Neck Plant, located in Middlesex
County, Connecticut. The license amendments are no longer required due
to the licensee's December 5, 1996, letter certifying permanent
cessation of operation and permanent offload of fuel from the reactor
vessel. The licensee withdrew the amendment requests in a letter dated
December 23, 1996.
The submittal date, subject, and Federal Register location (and
date of publication) for the previously issued Notice of Consideration
of Issuance of Amendment for the 18 proposed amendments being withdrawn
are listed below:
1. December 20, 1994; 24-Month Fuel Cycle--Steam Generator
Inspection Frequency; 60 FR 6574 (February 2, 1995)
2. October 20, 1995; 24-Month Fuel Cycle--Electrical Power Systems
Surveillance Extensions; 60 FR 65673 (December 20, 1995)
3. October 24, 1995; Limiting Safety System Settings; 60 FR 62488
(December 6, 1995)
4. October 27, 1995; Containment Isolation Valves; 60 FR 65675
(December 20, 1995)
5. November 1, 1995; 24-Month Fuel Cycle--Containment Isolation
Valves Surveillance Extensions; 60 FR 62488 (December 6, 1995)
6. December 4, 1995; 24-Month Fuel Cycle--Reactivity Control
Systems Surveillance Extensions; 61 FR 7548 (February 28, 1996)
7. December 19, 1995; 24-Month Fuel Cycle--Containment Air
Recirculation System Surveillance Extensions; 61 FR 7548 (February 28,
1996)
8. December 19, 1995; Dose Consequences Reanalysis and Containment
Pressure and Temperature Reanalysis; 61 FR 11229 (March 19, 1996)
9. December 19, 1995; 24-Month Fuel Cycle--Plant Systems
Surveillance Extensions; 61 FR 7548 (February 28, 1996)
10. December 20, 1995; 24-Month Fuel Cycle--Reactor Coolant Systems
Surveillance Extensions; 61 FR 7548 (February 28, 1996)
11. December 20, 1995; 24-Month Fuel Cycle--Instrumentation
Surveillance Extensions; 61 FR 7548 (February 28, 1996)
12. January 12, 1996, superseded by an April 16, 1996, letter;
Ultimate Heat Sink; 61 FR 28610 (June 5, 1996)
13. February 27, 1996; Turbine Cycle--Safety Valves; 61 FR 28608
(June 5, 1996)
14. February 28, 1996; Reactor Coolant System--Relief Valves; This
proposed amendment was not noticed in the Federal Register prior to the
withdrawal of the request.
15. March 7, 1996; Containment Air Recirculation System; This
proposed amendment was not noticed in the Federal Register prior to the
withdrawal of the request.
16. March 7, 1996; RH-MOV-808A (Replacement of Manual Valve with a
Motor-Operated Valve); 61 FR 28609 (June 5, 1996)
17. March 28, 1996; Reactor Coolant System Safety Valves; 61 FR
28609 (June 5, 1996)
18. April 22, 1996; 10 CFR Part 50, Appendix J, Primary Reactor
Containment Leakage Testing Requirements for Light-Water Cooled Power
Reactors Option B Performance-Based Requirements; 61 FR 28610 (June 5,
1996)
For further details with respect to this action, see the amendment
applications, and the licensee's letter dated December 23, 1996, which
withdrew the 18 license amendment applications. The above documents are
available for public inspection at the Commission's Public Document
Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and at
the local public document room located at the Russell Library, 123
Broad Street, Middletown, Connecticut 06457.
Dated at Rockville, Maryland, this 17th day of March 1997.
For the Nuclear Regulatory Commission.
Stephen Dembek,
Project Manager, Special Projects Office, Licensing Office of Nuclear
Reactor Regulation.
[FR Doc. 97-7337 Filed 3-21-97; 8:45 am]
BILLING CODE 7590-01-P
