ML20086B691
| ML20086B691 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/14/1995 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20086B692 | List: |
| References | |
| NUDOCS 9507060049 | |
| Download: ML20086B691 (5) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. 20066-0001 4,.....,o ENTERGY OPERATIONS. INC.
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DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated January 27, 1995, complies with the standards and requirements of the Atomic Encegy 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 conformity with the application, the provisions of the Act, and the rules and regulations of 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; i
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; i
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.
l 9507060049 950614 l
PDR ADOCK 05000382 l
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! 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby
-amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 108, and the Environmental Protection Plan a
contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the 3
Technical Specifications and the Environmental Protection Plan.
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3.
This license amendment is effective as of its date of issuance, and shall be implemented within 60 days from the date of its issuance.
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4 FOR THE NUCLEAR REGULATORY COMMISSION ffh Chandu P. Patel, Project Manager Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 14, 1995
l ATTACHMENT TO LICENSE AMENDMENT NO.108 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following page of the Appendix A Technical Specifications with the i
attached page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGE INSERT PAGE 5-5 5-5 i
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i DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSOtBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing a maximum of 236 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel length of 150 inches and contain a nominal total weight of 1830 grams uranium. The initial core loading shall have a l
maximum enrichment of 2.91 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading. Assemblies shall have a maximum enrichment of 4.9 weight percent U-235 provided they contain sufficient fixed poisons to meet the final storage requirements described in Section 5.6.
CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 83 full-length and 8 part-length control element assemblies.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
In accordance with the code requirements specified in Section 5.2 of a.
the FSAR with allowance for normal degradation pursuant of the applicable Surveillance Requirements, b.
For a pressure of 2500 psia, and For a temperature of 650*F, except for the pressurizer and surge line c.
which is 700*F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 11,800
+600, -0 cubic feet at a nominal T, of 582.l*F.
5.5 METEOROLOGICAL TOWERS LOCATION 5.5.1 The primary and backup meteorological towers shall be located as shown on Figure 5.1-1.
WATERFORD - UNIT 3 5-5 AMENDMENT NO. h 44,108
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DESIGN FEATURES i
5.6 FUEL STORAGE CRITICALITY
- 5. 6.2 The spent fuel storage racks are designed and shall be maintained with:
A k,77 equivalent to less than or equal to 0.95 when flooded with a.
unborated water uncertainties., which includes a conservative allowance for b.
A nominal 10.38 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks.
5.5.2 The k,9f for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
i DRAINAGE 5.6.3 inadvertent draining of the pool below elevation +40.0 MSL.Th CAPACITY 5.6.4 The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 1088 fuel assemblies.
- 5. 7' COMPONENT CYCLIC OR TRANSIENT LIMITS 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.
j WATERFORD - LMIT 3 5-6 AMENDMENT no. 7' 44
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