ML20205B972
| ML20205B972 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/19/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205B976 | List: |
| References | |
| NUDOCS 8810260354 | |
| Download: ML20205B972 (6) | |
Text
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- p+**te%jo UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION c
-l WASHINGTON. D. C. 20666
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LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAh ELECTRIC STAT 10Nn LNIL3 t
AftENt#ENT TO FACILITY OPFRATING LICENSE t
Arnendirent No. 44 License No. NPF-38 1.
The Nuclear ReCulatory Conission (the Contnission) has found that:
A.
The application for an<endrent by Louisiana Power and Light Conpany (the licensee) dateo July 18, 1988, con plies with the standards and requirenents of the Atortic Energy Act of 1954, as anended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confortrity with the application, the provisiers of the Act, and the rules and regulations of the Comission; C.
There is ressenable assurance (1) that the activities authorized by this anendnent r.an be conducted without endangering the health and safety of the public, and (ii) that such activities will be ccnducted in cortpliar.cc with the Cont.iission's regulations; D.
The issuanco of this anendnent will nct be inirnical to the conson defense and security or to the health and safety of the public; arid E.
The issuance of this anendnent is in accordance with 10 CFR Part 51 of the Conenission's regulations and all applicable requirerrents have been satisfieo.
ss10260354 881019
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. 2.
Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachment to this license amendment,andparagraph2.C(2)ofFacilityOperatingLicenseNo.
NPF-38 is hereby arnended to read as follows:
(2) Technical Specifications and Environmental Protection Plar.
The Technical Specifications contained in Appendix A, as revised thrcugh Amendment No.
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendnent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION sbnv v Jose A. Calvo. Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation Attachn.ent:
1 Changes to the Technical Specifications Cate of Issuance: October 19, 1988
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r ATTACWENT T_ O LICENSE AMENDMENT NO. 44 i
i TO FACILITY OPERATING LICENSE N0. NPF-38 DOCKET NO. 50-3P2 Replace the following page of the Aprendix A Technical Specific.ations with the attached page. The revised page is identified by Amendment
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number and contains a vertical line indicating the area of change. The corresponding overleaf page is also provided to raintain document completeness.
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' Pemove Insert 5-5 5-5 l
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 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 fuei rod shall nave a nominal active fuel length of 150 inches and contain a nominal total weight of 1807 grams uranium.
The initial core loading shall have a maximum enrichment of 2.91 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.1 weight percent U-235.
l 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 i
DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable Surveillance Requirements, b.
For a pressure of 2500 psia, and c.
For a temperature of 650'F, except for the pressurizer and surge line 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,yg of 582.1*F.
- 5. 5 METEOROLOGICAL TOWERS LOCATION 5.5.1 The primary and backup meteorological towers shell be located as shown on Figure 5.1-1.
WATERFORD - UNIT 3 5-5 AMENDMENT NO. 7,44
s DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to e ;J when flooded with a.
unborated water, which includes a conservative allowance for uncertainties.
b.
A nominal 10.38 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks.
5.6.2 The k,ff 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.
DRAINAGE 5.6.3 The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation +40.0 MSL.
CAPACITY 5.6.4 The spent fuel pool is designed and shall be raintained 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.
I WATERFORD - UNIT 3 5-6 AMENDMENT NO. 7. 44
PESIGNFEATURES 5.6 FUEL STORAGE CRI1!CALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance for uncertainties.
b.
A nominal 10.38 inch center-to-cent'ar distance between fuel assemblies placed in the spent fuel storage racks.
5.6.2 The k,ff 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.
DRAINAGE 5.6.3 The sptnt fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation +40.0 MSL.
CAPACITY 5.6.4 The spent fuel pool is designef snd shall be maintained with a storage capacity limited to no more
- An 1088 fuel assemblies.
l 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be l
maintained within the cyclic or transient limits of Table 5.7-1.
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WATERFORD - UNIT 3 5-6 AMENDMENT NO. 7. 44 i
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