ML20140H879
| ML20140H879 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/09/1997 |
| From: | Reinhart M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20140H883 | List: |
| References | |
| NUDOCS 9705130304 | |
| Download: ML20140H879 (10) | |
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 206d54001
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-318 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 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 September 4,1996, as supplemented by letter dated February 3, 1997, 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 be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in comoliance 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.
9705130304 970509 PDR A00CK 05000338 PDR 7,,P _, _
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L 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.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. 204, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Also, the license is amended by replacing Paragraph 2.D,3.(d) on page 4 of Facility Operating License NPF-4 with the following:
d.
Virginia Electric and Power Company may use up to four (4) fuel assemblies containing advanced zirconium based alloys as described in the licensee's submittal dated September 4,1996, as supplemented February 3, 1997.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION f
Mark Reinhart, Acting Director Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
1.
Page 4 of License NPF-4 2.
Changes to the Technical Specifications Date of Issuance: May 9,1997
'Page 4 is attached, for convenience, for the composite license to reflect this change, l
l '
(1)
Maximum Power Level I
VEPCO is' authorized to operate the North Anna Power Station, Unit No.
1, at reactor core power
{
1evels not in excess of 2893 megawatts (thermal).*
4 (2)
Technical Soecifications The Technical Specifications contained in i
Appendices A and B, as revised through Amendment No. 204, are hereby incorporated in the license.
i VEPCO shall operate the facility in accordance 1
l with the Technical Specifications.
)
j (3)
Additional Conditions f.
The matters specified in the following conditions i
shall be completed to the satisfaction of the Commission within the stated time periods I
following the issuance of this amendment or within l
the operational restrictions indicatsd.
The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission:
c.
Virginia Electric and Power Company shall not operate the reactor in operational modes 1 and 2 with less than three reactor ecolant pumps in operation.
d.
Virginia Electric and Power Company may use up to'four (4) fuel assemblies containing advanced zirconium based alloys as described in-the licensee's submittal dated September 4, 1996, as supplemented February 3, 1997.
e.
If Virginja Electric and Power Company plans 4
to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the North Anna Station, the Commission shall be notified in writing regardless of whether the change affects the amount of radioactivity in the effluents.
- The maximum reactor power level shall be limited to 2748
.wegawatts (thermal) which is 95% of RATED THERMAL POWER in accordance with the licensee's submittal dated January 28, 1992 (Serial No.92-042) for the period of operation until the steam generator replacement.
Amendment No. 44, -44.,
44, 44-1.,
wa, 204
ATTACHMENT TO LICENSE AMENDMENT N0. 204 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 a vertical line indicating the area of change.
Remove Paae Insert Paae 5-4 5-4
DESIGN FEATURES 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.
il REACTOR CORE FUEL ASSEMBLIES j
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 length of 144 inches. 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 i
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. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core locations.
CONTROL ROD ASSEMBL1ES 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.
14 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
NORTH ANNA - UNIT 1 54 A...endment No. M, 27,36,127, 183,'86,204
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 3066H001 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE j
DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 185 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensae) dated September 4, 1996, as supplemented by letter dated February 3,1997, 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 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 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.
)
b 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 amended to read as follows:
(2) Technical Soecifications 1
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 185, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Also, the license is amended by adding new Paragraph 2.C.(24) on page 12a of Facility Operating License NPF-7 as follows:*
2.C.(24)
Lead Test Assemblies Virginia Electric and Power Company may use up to four (4) fuel assemblies containing advanced zirconium based alloys as described in the licensee's submittal dated Septemuer 4, 1996, as supplemented February 3, 1997.
4.
This license amendment is effective as of its date of issuance and shall i
be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION A
Mark Reinhart, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
i 1.
Page 12a of License NPF-7 l
2.
Changes to the Technical l
Specifications Date of Issuance:
May 9~,1997 i
I
'Page 12a is attached, for convenience, for the composite license to reflect this change.
l
1
- 12a -
2.C.(23)
Fire Protection VEPCO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated February 1979 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain Isafe shutdown in the event of a fire.
2.C.(24)
Lead Tgst Assemblies Virginia Electric and Power Company may use up to four (4) fuel assemblies containing advanced zirconium based alloys as described in the licensee's submittal dated September 4, 1996, as supplemented February 3, 1997.
D.
An exemption from certain requirements of Appendix J to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 10.
This exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest.
The exemption is,'therefore, hereby granted.
The granting of the exemption was authorized with the issuance of the License for Fuel-Loading and Low-Power Testing, dated April 11, 1980.
The facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the regulations of the commission.
Amendment No. H4,185
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1 ATTACHMENT TO LICENSE AMENDMENT N0. 185 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 4
Replace the following page of the Appendix "A" Technical Specifications with i
the enclosed page as indicated. The revised page is identified by amendment number and contains a vertical line indicating the area of c~ange.
n Remove Paae Insert Paae 5-4 5-4 1
i i
i t
4 i
4 4
a d
DESIGN FEATURES M
BEACTOR 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 or ZIRLO. 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 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. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core locations.
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.
M 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 approximately 10,000 cubic feet at nominal operating conditions.
NORTH ANNA - UNIT 2 5-4 Amendment No. 8, !6, ! ! !, "6, 15?,'67,185
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