ML20057F819
| ML20057F819 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/14/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057F820 | List: |
| References | |
| NUDOCS 9310190189 | |
| Download: ML20057F819 (7) | |
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UNITED STATES ~
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,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 4, -
,o DUOVESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.177 License No. DPR 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Lig.t Company, et al.-(the
. licensee)-dated June 11, 1993, as supplemented October 8, 1993, complies with the standards and requirements of the Atomic Energy L
Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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9310190189 931014 PDR ADOCK 05000334' P
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2.
Accordingly,.the license is amended by changes to the Technical j
Specifications as indicated in the attachment to this license amendment,.
and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended'to read as follows:
j (2) Technical Specifications i
The Technical Specifications contained in Appendix A, as revised.
i through Amendment No. 177, 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 its issuance, to be implemented prior to loading a reconstituted fuel assembly into the core, or within 60 days of issuance, whichever occurs first.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II.
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 14, 1993 P
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ATTACHMENT TO LICENSE AMENDMENT N0.177 FACILITYbPERATINGLICENSENO.DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number ano contain vertical lines indicating the areas of change.
Remove Insert 5-4 5-4
DPR-66 DESIGN FEATURES
.7 DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 45 psig and a temperature of 280*F.
PJJETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 5.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 157 fuel assemblies.
Each assembly shall consist of a matrix of zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material.
Limited substitutions of zirconium alloy or 2
stainless steel filler rods for fuel rods, in accordance with 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 Jethods 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.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length and no part 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 percent silver, 15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
BEAVER VALLEY - UNIT 1 5-4 Amendment No.177 I
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UNITED STATES y-Il j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205564001
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DVOUESNE LIGHT COMPAN1 OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILI.UMINATING COMPANY THE TOLEDO EDIS0N COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. NPF-73 1.
The Nuclear Regulatcry Comission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated June 11, 1993, as supplemented October 8, 1993, complies with the standards and requirements of the Atomic Energy j
Act of 1954, as amended (the Act) and the Comission's rules and 1
t regulations set forth in 10 CFR Chapter I; I
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the
)
Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be condteted without endangering the health and safety of the public, and (ii) that such activitier. will be conducted in compliance with the Comission'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 Comission's regulations and all applicable requirements f
have been satisfied.
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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, and paragraph 2.C.(2) of Facility Operating License'No. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications The. Technical Specifications contained in Appendix A,' as revised through Amendment No. 58, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. OLC0 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 prior to-loading a reconstituted fuel assembly into the' core, or within 60 days of issuance, whichever occurs first.
FOR THE NUCLEAR REGULATORY COMMISSION f Gl Y
l Walter R. Butler, Director Project Directorata I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
I Changes to the Technical Specifications Date of Issuance:
October 14, 1993 t
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ATTACHMENT TO LICENSE AMENDMENT N0.58 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 5-6 5-6 5-7 5-7 l
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j NPF-73 DESIGN FEATURES i
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for maximum internal pressure of 45 psig and a temperature -
of 280.0*F.
j PENETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE I
FUEL ASSEMBLIES 5.3.1 The reactor shall contain 157 fuel assemblies.
Each assembly shall consist of a matrix of zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material.
Limited substitutions of zirconium alloy or 2
stainless steel filler rods for fuel rods, in accordance with 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.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length and no part 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 percent silver, 15 percent indium and 5 percent cadmium.
All control rods shril be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE i
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 to the applicable Surveillance Requirements, BEAVER VALLEY - UNIT 2 5-6 Amendment No. 58 i
NPF-73 DESIGN FEATURES 5.4 REACTOR COOLANT SYSTEM (Continued) b.
For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizor which is 680*F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 9370 cubic feet at a nominal T,y of 576*F.
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 STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be l
maintained with a minimum of 10.4375 inch center-to-center distance between fuel assemblies placed in the storage racks. The fuel will be stored in accordance with the provisions described in FSAR Sections 4.3 and 9.1 to ensure a k.tr equivalent to 50.95 with the storage pool filled with unborated water.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 751'-3".
t CAPACITY l
5.6.3 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1083 fuel assemblies.
5.7 SEISMIC CLASSIFICATION 5.7.1 Those structures, systems and components identified as Category I items in Section 3.7 of the FSAR shall be designed and maintained to the original design provisions with allowance for normal degradation pursuant to the applicant surveillance Requirements.
5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorological towe.r shall be located as shown on Figure 5.1-1.
BEAVER VALLEY - UNIT 2 5-7 Amendment No. 58 t
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