ML20117K403
| ML20117K403 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/05/1996 |
| From: | Imbro E NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20117K406 | List: |
| References | |
| NUDOCS 9606110197 | |
| Download: ML20117K403 (9) | |
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-4 UNITED STATES
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555-4001
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 201 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 January 30, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as l
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 l
Commission; 1
C.
There is reasonable assurance (i) that the cctivities 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 l
l defense and security or to the health and safety of the public; and i
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 been satisfied.
l l
9606110197 960605 PDR ADOCK 05000338 P
. 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.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. 201, 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 NUCLEAR REGULATORY COMMISSION d
Eugene V. Imbro, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 5,1996 4
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ATTACHMENT 0 ICENSE AMENDMENT NO. 201
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TO FACILITY OPEkATING LICENSE N0. NPF-4
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DOCKET 'fl0. 50-338
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Replace the following page of the Appendig "A" Technical Specifications with the enclosed page as indicated. The revis'ed page is identified by amendment number and contains vertical lines indicatilig the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
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ZOW TABLE 3.2-1 y
DNB PARAMETERS g
LIMITS a
2 Loops in Operation **
2 Loops in Operation **
3 Loops in
& Loop Stop
& Isolated Loop PARAMETER Operation Valves Open Stop Valves Closed Reactor Coolant System T s 591 F avs Pressurizer Pressure 2 2205 psig
- Reactor Coolant System 2 295,000 gpm l
w Total Flow Rate w
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G Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% RATED THERMAL POWER per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL POWER.
Values dependent on NRC approval of ECCS evaluation for these conditions.
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$ W 9602020141 960130 PDR ADOCK 05000338
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w THIS PAGE DELETED i
f.0RTH ANNA - UNIT 1 3/4 2.16 Amendment Ho, 3,5,18 !!
37.39,45,84, 105 l
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lq UNITED STATES f
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055H001 o
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 l
NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.182 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-licensee) dated January 30, 1996, complies with the l
standards and requirements of the Atomic Energy Act of 1954, as i
amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
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 iss;ance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l l
A
. 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 heceby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 182 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 NUCLEAR REGULATORY COMMISSION
[
Vm Eugene V. Imbro, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 5, 1996
ATTACHMENT TO LICENSE AMENDMENT NO. 182 l
TO FACILITY OPERATING LICENSE NO. NPF-7 i
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.
l Remove Paae Insert Paae 3/4 2-16 3/4 2-16 I
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4 ZO
- o-I 3:
g TABLE 3.2-1 DNB PARAMETERS C
LIMITS 24 2 Loops in Operation **
2 Loops in Operation **
w 3 Loops in
& Loop Stop
& Isolated Loop PARAMETER Operation Valves Ooen Sigo Valves Closed Reactor Coolant System T,yg s591 F Pressurizer Pressure 2 2205 psig
- Reactor Coolant System 2 295,000 gpm j
ta Total Flow Rate 3:
E Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% RATED THERMAL POWER per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL POWER.
Values dependent on NRC approval of ECCS evaluation for these conditions.
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