ML20078K701
| ML20078K701 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/08/1994 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078K702 | List: |
| References | |
| NUDOCS 9411230311 | |
| Download: ML20078K701 (4) | |
Text
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UNITED STATES I
E NUCLEAR REGULATORY COMMISSION i
iI WASHINGTON. D.C. 201 4 4001
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET N0. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT N0. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 182 License No. DPR 65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated September 1,1994, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) 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; 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.
4 9411230311 941100 i
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. 3 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and. paragraph 2.C.(2) of Facility Operating License No. DPR-65 is -hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained-in Appendix A, as revised through Amendment No.182, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Phillip F. McKee, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications Date of Issuance: November 8, 1994 i
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ATTACHMENT T0 LICENSE AMEN 0 MENT NO.182 FACILITY OPERATING LICENSE NO. OPR-65 DOCKET N0. 50-336 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contain a vertical line indicating the area of change.
Remove Insert 5-5 5-5
a DESIGN FEATURES VOLVME 5.4.2 The total water and steam volume of the reactor coolant system is a nominal 10,981 f t*.
5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAG_E CRITICALITY 5.6.1 a)
The new fuel (dry) storage racks are designed and shall be maintained with sufficient center to center distance between assemblies to ensure a k,n s.95.
The maximum nominal fuel enrichment to be stored in these racks is 4.50 weight percent of U-235.
b)
Region A of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations to ensure a K,n s.95 with the storage pool filled with unborated water. Fuel assemblies stored in this region must comply with Figure 3.9-4 to ensure that the design burnup has been sustained.
c)
Region 8 of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center-to-center distance between storage locations to ensure K,n s.95 with a storage pool filled with unborated water.
Fuel assemblies stored in this region may have a maximum nominal enrichment of 4.5 weight percent U-235. Fuel assemblies stored in this region are pit,ced in a 3 out of 4 STORAGE PATTERN for reactivity centrol.
d) Region C of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations to ensure a K,n s.95 with the storage pool filled with unborated water.
Fuel assemblies stored in this region must comply with Figures 3.9-la or 3.9-lb to ensure that the design burn-up has been sustained.
Additionally, fuel assemblies utilizing Figure 3.9-lb require that borated stainless steel i
poison pins are installed in the fuel assembly's center guide tube and in two diagonally opposite guide tubes.
The poison pins are solid 0.87 inch 0.D.
borated stainless steel, with a boron content of 2 weight percent boron.
e)
Region C of the spent fuel storage pool is designed to permit storage of consolidated fuel and ensure a K,y 1 0.95.
The contents of consolidated fuel storage boxes to be stored in this region must comply with Figure 3.9-3.
MILLSTONE - UNIT 2 5-5 Amendment No. 79, JJ. 197, otss 117,199,IFF, J/g,182
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