ML20043F713
| ML20043F713 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/06/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043F715 | List: |
| References | |
| NUDOCS 9006180035 | |
| Download: ML20043F713 (9) | |
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UNITED STATES
.c NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20655
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING 1.ICENSE Amendment No.127 License No. NPF-4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.-
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated September 30, 1988, as supplemented August 18, 1989, complies with the standards and requirements of the Atomic Energy 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-isreasonableassurance(i)thattheactivitiesauthorized-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 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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Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. NpF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.127, 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION He ert N. Berkow, Director Project Directorate II-2 t
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
~l Changes to the Technical Specifications Date of Issuance: June 6, 1990 i
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i ATTACHMENT TO LICENSE AMENDMENT NO. 127 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following page of the Appendix "A" Technical Specifications with-the enclosed page as indicated. The revised page is identified by amendment i
number and contains vertical lines indicating the area of change,
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1780 grams uranium. The initial core loading shall have a maximum enrichment of 3.2 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrich-ncnt of 4.3 weight percent U-235.
l CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 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 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing..
4 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 code 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 9957 + 10 cubic feet at a nominal T,yg of 525"F.
NORTH ANNA - UNIT 2 5-4 Amendment No. B, )$,111
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
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WASHING TON, D. C. 20666 l
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j VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENOMENT TO FAClllTY OPERATING LICENSE Amendment No.111 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:'
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated September 30, 1988, as supplemented August 18, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in-10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of l
the Comission; 1
l C.
There is reasonable assurance (1) that the activities authorized i
by this amendment can be conducted without endangering the health i
and safety of the public, and (ii) that such activities will be i
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.
4 2.
Accordingly, the license is amended by changes to the Technical Speci-I fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating Licenso No. NPF-7 is hereby amended to read as follows:
(21 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 111
, 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
(?
I He ert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
- Date of Issuance: June 6, 1990 4
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ATTACHMENT TO LICENSE AMENOMENT N0.111 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339
. Replace the following page of.the Appendix "A" Technical Specifications with the-enclosed page as indicated. The revised page is identified by amendment nunber and contains vertical lines indicating the area of change.
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l M N - WIT 2 5-3 Amendment No. 3J,53 i:
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OESIGN FEATURES 5.3 REACTOR CORE-FUEL ASSEMBL!ES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1780 grams uranium. The initial core loading shall have a maximum enrichment of 3.2 weight percent U-235.
Reload fuel shall be similar in physical dec1gn to the initial core loading and shall have a maximum enrich-ment of 4.3 weight percent U-235.
l CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 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 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEliPERATURE 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, 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 9957 f.10 cubic feet at a nominal T,yg of 525'F.
t NORTH ANNA - UNIT 2 5-4 Amendment No. 8,)$,111 l
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