ML20216G867
| ML20216G867 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/16/1998 |
| From: | Kuo P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216G872 | List: |
| References | |
| NUDOCS 9804200515 | |
| Download: ML20216G867 (8) | |
Text
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i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION I
WASHINGTON. D.C. 30666-0001 o,s...../
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. 210 License No. NPF-4 1.
The Nucle 6r Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated November 18, 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.
98o4200515 98o416 PDR ADOCK 0500o338 P
2 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 Snecifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 210. are hereby incorporated in the license. The licensee shall operate the facility ~ in accor' dance 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 I
P T.
Kuo. Acting Director roject Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 16,1998 I
ATTACHMENT TO LICENSE AMENDMENT NO: 210 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 3/4 7-15 3/4 7-15 i
PLANT SYSTEMS j
TURBINE OVERSPEFIT LIMITING CONDITION FOR OPERATION 3.7.1.7 At least one turbine overspeed protection system shall be OPERABLE.
APPI.ICABTI TTY-MODE 1,2 and 3 I
ACTION-With the above required turbine overspeed protection system inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENT.
4.7.1.7.1 The provisions of Specification 4.0.4 are not applicable.
4,7.1.7.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
By cycling each of the following valves through at least one complete cycle from a.
the running position and verifying movement of each of the valves through one complete cycle from the running position by direct observation:
1.
Four Turbine Throttle valves at least once per 92 days, 2.
Four Turbine Governor valves at least once per 92 days,
- 3.
Four Turbine Reheat Stop valves at least once per 18 months, and 4.
Four Turbine Reheat Intercept valves at least once per 18 months.
b.
At least once per 18 months, by performance of CHANNEL CALIBRATION on the turbine overspeed protection instruments.
c.
At least once per 40 months * *, by disassembly of at least one of each of the above valves and performing a visual and surface inspection of all valve seats, disks and stems and verifying no unacceptable flaws or corrosion. If unacceptable flaws or excessive corrosion are found, all other valves of that type shall be inspected unless the nature of the problem can be attributed to a service condition specific to that valve.
Testing of the turbine governor valves may be suspended during end-of-cycle power coastdown operation between 835 MWe and 386 MWe.
- For reheat stop and reheat intercept valves, the inspection cycle may be increased to a maximum of once per 60 months provided there is no indication of operational distress.
NORTH ANNA - UNIT 1 3/4 7-15 Amendment No. 16,56,136,195, 307, 210
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'4 UNITED STATES g
NUCLEAR REGULATORY COMMISSION g
WASHINGTON. D.C. 30666 4 001
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l VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.191 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 November 18, 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 i
Commission:
C.
There is reasonable assurance (1) 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.
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 amended to read as follows:
(2) Technical Soecifications The. Technical Specifications contained in Appendices A and B. as revised through Amendment No.191
. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical cpecifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION W
T.
Kuo. Acting 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:
April 16,1998
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ATTACHMENT TO LICENSE AMENDMENT NO.191 i
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 ^
number and contains a vertical line indicating the area of change.
Remove Pace Insert Paae 3/4 7-12 3/4 7-12 i
l I
l l
~
PI ANT SYSTEMS TimRINE OVERSPEED LIMITING CONDITION FOR OPERATION 3.7.1.7 At least one turbine overspeed system shall be OPERABLE.
l 4
APPI ICARIT ITY-MODE 1,2 and 3 ACTION-With the above required turbine overspeed protection system inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENT 4.7.1.7.1 The provisions of Specification 4.0.4 are not applicable.
i 4.7.1.7.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
By cycling each of the following valves through at least one complete cycle from a.
the running position and verifying movement of each of the valves through one complete cycle from the running position by direct observation:
1.
Four Turbine Throttle valves at least once per 92 days, 2.
Four Turbine Governor valves at least once per 92 days,
- I 3.
Four Turbine Reheat Stop valves at least once per 18 months, and 4.
Four Turbine Reheat Intercept valves at least once per 18 months.
- b. '
At least once per 18 months, by performance of CHANNEL CALIBRATION on the turbine overspeed protection instruments.
c.
At least once per 40 months * *, by disassembly of at least one of each of the above valves and performing a visual and surface inspection of all valve seats, disks and stems and verifying no unacceptable flaws or corrosion. If unacceptable flaws or excessive corrosion are found, all other valves of that type shall be inspected unless the nature of the problem can be attributed to a service condition specific to that valve.
Testing of the turbine governor valves may be suspended during end-of-cycle power coastdown operation between 835 MWe and 386 MWe.
' ** For reheat stop and reheat intercept valves, the inspection cycle may be increased to a maximum of once per 60 months provided there is no indication of operational distress.
. NORTH ANNA - UNIT 2 3/4 7-12 Amendment No. 38,8!, ! !9, !?6, 448, 191