ML20141B978
| ML20141B978 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/13/1997 |
| From: | Milano P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141B981 | List: |
| References | |
| NUDOCS 9705160091 | |
| Download: ML20141B978 (5) | |
Text
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION i
2 WASHINGTON, D.C. 20seH001
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i NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL*
DOCKET N0. 50-443 SEABROOK STATION. UNIT NO.]
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. NPF-86 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated February 18, 1997, as supplemented by letter dated February 26, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in tonformity with the applicatf on, the provisions of the Act, and the rules and regulations ad the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; j
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment-is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- North Atlantic Energy Service Company (NAESCO) is authorized to act as agent for the: North Atlantic Energy Corporation, Canal Electric Company, The Connecticut Light and Power Company, Great Bay Power Corporation, Hudson Light and Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, and The United Illuminating Company, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
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Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No, NPF-86 is hereby amended to read as follows:
l (2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 51, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No.
NAESCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION JM Patrick A. Milano, Acting Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance: May 13, 1997
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ATTACHMENT TO LICENSE AMENDMENT NO. 51 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of Appendix A, Technical Specifications, with the-attached pages as indicated. The revised pages are identified by amendment number and contain verticp1 lines indicating the areas of change. Overleaf pages have been provided Remove Insert 5-9 5-9 5-10*
5-10*
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DESIGN FEATURES i
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 52.0 psig and a temperature of 296*F.
5.3 REACTOR CORE FUEL ASSEMBLIES
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5.3.1 The reactor shall contain 193 fuel assemblies.
Each assembly shall consist of a matrix of cylindrical zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (00 ) as fuel 2
material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80% silver,15%
indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Ccde requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,255 cubic feet at a nominal T of 588.5'F.
m 5.5 (THIS SPECIFICATION NUMBER IS NOT USED) i SEABROOK - UNIT 1 5-9 Amendment No. 51
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DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
A k,,,ted water, which includes margin for uncertainty inequivalent to le a.
unbora calculation methods and mechanical tolerances with a 95%
probability at a 95% confidence level.
b.
A nominal 10.35 inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.1.2 The new fuel storage racks are designed and shall be maintained with:
A k,,,ted water, which includes margin for uncertainty inequivalent to le a.
unbora calculational methods and mechanical tolerances with a 95%
probability at a 95% confidence level.
A k,,, tion is assumed, which includes margin for uncertainty inequivalen b.
modera calculational methods and mechanical tolerances with a 95%
probability at a 95% confidence level.
c.
A nominal 21 inch center-to-center distance between fuel assemblies placed in the storage racks.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 14 feet 6 inches.
l CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1236 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
l SEABROOK - UNIT 1 5-10 Amendment No. 6
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