ML20072A105
| ML20072A105 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/09/1994 |
| From: | Mccree V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072A108 | List: |
| References | |
| NUDOCS 9408120134 | |
| Download: ML20072A105 (8) | |
Text
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.i p* REG ye 4
UNITED STATES j
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555-0001
,o VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.186 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated November 19, 1993, 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; 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 (i) that the activities authorized by this amendment can ba 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.
9408120134 940809 PDR ADOCK 05000338 P
e s 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license imendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.186, 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 its date of issuance and shall be implemented within 30 days.
FOR THE R REGULATORY COMMISSION I'
Victor M. Mc ree, Ac ing Director Project Dir torate JI-2 Division of actor (ojects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 9, 1994
ATTACHMENT TO LICENSE AMENDMENT NO.186 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 number and contains vertical lines indicating the area of change.
Remove Paae Insert Paae 5-4 5-4
^
DESGN FEATURES DESIGN PREERURE ANDTEMPERATURE 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.
53 REACTORCORE BIELASSEMBLlES 5.3.1 The reactor oore shall contain 157 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4 or ZlRLO. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.2 weight l
percent U 235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent U 235. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those 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.
CONTROL ROD ASSEhELIES 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 REACTORCOOLANTSYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
NORTH ANNA - UNIT 1 54 Amendment No. 76, 27, 36, 727, 783, 186
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lo-d UNITED STATES l
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[h.lifi, j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555 4001 j
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VIRGINIA ELECTRIC AND POWER COMPANY i
4 OLD DOMINION ELECTRIC COOPERATIVE 4
4 DOCKET NO. 50-339 1
NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No.167 j
License No. NPF-7 y
1.
The Nuclear Regulatory Commission (the Commission) has found that:
i i
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated November 19, 1993, complies with the 3
standards and requirements of the Atomic Energy Act of 1954, as 1
amended (the Act), and the Commission's rules and regulations set l
forth in 10 CFR Chapter I; I
B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the l
Commission; i
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and j
safety.of the public, and (ii) that such activities will be conducted in compliance with the CommissioC ; regulations; Y
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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have 1
been satisfied.
j
)
1 4
)
i 3
4
I l l 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby l
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as l
revised through Amendment No. 167, are hereby incorporated in the license.
The licensee shall operate the facility in accordance l
with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall l
be implemented within 30 days.
l FOR THE LEAR REGULATORY COMMISSION Al Victor M. McC ee, Ac ing Director Project Directorate 1 2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical Specifications Date of Issuance: August 9, 1994 l
l
l ATTACHMENT TO LICENSE AMENDMENT NO.167 TO FACILITY OPERATING LICENSE 10. 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 number and contains vertical lines indicating the area of change.
Remove Pace Insert Pace 5-4 5-4 i
j i
l l
)
t l
l t
I l
DESGN FEATURES j
i 53 REACTORCORE FUEL ASSEMBUES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy 4 or ZlRLO. Each fuel rod shall have a nominal active fuel i
length of 144 inches. The initial core loading shall have a maximum enrichment of 3.2 weight 1-percent U 235. Relo&d fuel shall be similar in physical design to the initial core loading and i
shall have a maximum enrichment of 4.3 weight percent U-235. - Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those 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.
COMROLRODASSEhELIES 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 ANDTEMPERATURE 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 approximately 10,000 cubic feet at nominal operating conditions.
NORTH ANNA - UNIT 2 5-4 Amendment No. E, 76, 777, 7#6, 76f,
167
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