ML20097D223
| ML20097D223 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/08/1996 |
| From: | Matthews D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20097D229 | List: |
| References | |
| NUDOCS 9602120262 | |
| Download: ML20097D223 (10) | |
Text
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.4 UNITED STATES y
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20066-0001 l
'+,*****,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 I
Amends'nt No. 195 e
License No. NPF-4 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power 4
Company et al., (the licensee) dated September 19, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and I
i 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; 1
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 comon 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 i
51 of the Commission's regulations and all applicable requirements have been satisfied.
l 9602120262 960208 DR ADOCK 0500 0
. 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 fcilows:
(2) Technical Snecifications J
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.195, 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 N CLEAR REGULATORY COMMISSION David
. Matthews, Director i
1 Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 8,1996 i
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1 ATTACHMENT TO LICENSE AMENDMENT NO.195 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 i
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.
The corresponding overleaf page is also provided-to maintain document completeness.*
Remove Paaes Insert Paaes 3/4 7-15 3/4 7-15*
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3/4 7-16 3/4 7-16 f
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PLANT SYSTEMS TURBINE OVERSPEED LIMITING CONDITION FOR OPERATION 3.7.1.7 At least one turbine overspeed protection system shall be OPERABLE.
AffLICABILITY:
MODE 1,2 and 3 ACTION:
With the abooe 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 one complete cycle of full travel a.
and verifying movement of each of the valves through one complete cycle by direct observation:
1.
Four Turbine Throttle valves at least once per 31. days, j
2.
Four Turbine Governor valves at least once per 31 days,
- l 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 instmments.
i c.
At least once per 40 months ", by disassembly of at least one of each of the above l
valves and performing a visual and surface inspection of all valve seats, disks and 4
j stems and verifying no unacceptable flaws or corrosion. If unacceptable flaws or j
excessive corrosion are found, all other valves of that type shall be inspected unless i
the nature of the problem can be attributed to a service condition specific to that j
valve.
Testing of the turbine govemor valves may be suspended during end-of-cycle power l
coastdown operation between 835 MWe and 386 MWe.
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" 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 I 3/4715 Amendment No. !6. 55.135,195 4
4 PLANT SYSTEMS i
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION 2
LIMITING CONDITION FOR OPERATION i
3.7.2.1 The temperatures of both-the primary and secondary coolants in
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the steam generators shall be > 70*F when the pressure of either coolant I
in the steam generator is > 200 psig, n
APPLICABILITY: At all times.
I ACTION:
With the requirements of the above specification not satisfied:
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a.
Reduce the steam generator pressure of the applicable side to J-
< 200 psig within 30 minutes, and i
Perform an engineering evaluation to determine the effect of b.
the overpressurization on the structural integrity of the l
steam generator. Determine that the steam generator remains i
acceptable for continued operation prior to increasing its t
temperatures above 200'F.
I SURVEILLANCE REQUIREMENTS i
4.7.2.1 The pressure in each side of the steam generator shall be determined to be < 200 psig at least once per hour when the temperature of either the primary or secondary coolant is < 70*F.
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i-NORTH ANNA - UNIT 1 3/4 7-16
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UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20666-0001
'+9.....,o VIRGINIA ELECTRIC AND POWER COMPANY j
OLD DOMINION ELECTRIC COOPERATIVE j
DOCKET NO. 50-339 i
NORTH ANNA POWER STATION. UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 176 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated September 19, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 1
regulations set forth in 10 CFR Chapter I; 4
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the e
Commission; 1
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 j
conducted in compliance with the Commission's regulations; i
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 j
51 of the Commission's regulations and all applicable requirements have been satisfied.
i
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i
1 i
t ;
j 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and 4
i paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
4 l
(2) Technical Snecifications l
The Technical Specifications contained in Appendices A and B, as i
revised through Amendment No. 176, are hereby incorporated in the j
license. The licensee shall operate the facility in accordance j
with the Technical Specifications.
i 3.
This license amendment is effective as of its date of issuance and shall j
be implemented within 30 days.
FOR THE NUCLEAR REGULATORY C0ftilSSION l
David B. Matthews, Director i
Project Directorate II-l l
Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation f
Attachment:
Cnanges to the Technical Specifications Date of Issuance: February 8,1996 i
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l ATTACHMENT TO LICENSE AMENDMENT NO. 176 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 vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.*
Ramave Paaes Insert Paaes 3/4 7-11 3/4 7-11*
3/4 7-12 3/4 7-12 l
1 PLANT SYSTEMS STEAM TURBINE ASSEMBLY I
LIMITING CONDITION FOR OPERATION 3.7.1.6 The structural integrity of the steam turbine assembly shall be maintained.
APPLICABILITY: MODES 1 and 2 ACTION: With the structural integrity of the steam turbine assembly not con-forming to the_above requirement restore the structural integrity of the steam turbine prior to placing it in service.
SURVEILLANCE REQUIREMENTS 4.7.1.6 The structural integrity of the steam turbine assembly shall be 1
demonstrated;
'a.
At least once per 4u months, during shutdown, by a visual and surface inspection of the steam turbine assembly at all accessible locations, and b.
At least once per 10 years, during shutdown, by disassembly of the turbine and performing a visual, surface and volumetric inspection of all normally inaccessible parts.
1 NORTH ANNA - UNIT 2 3/4 7-11
PLANT SYSTEMS TURBINE OVERSPEED LIMITING CONDITION FOR OPERATION i
3.7.1.7 At least one turbine overspeed system shall be OPERABLE.
l APPLICABILITY:
MODE 1,2 and 3 j
ACTION:
1 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 l
4.7.1.7.1 The provisions of Specification 4.0.4 are not applicable.
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i 4.7.1.7.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
1 1
a.
By cycling each of the following valves through one complete cycle of full travel i
i and verifying movement of each of the valves through one complete cycle by direct l
observation:
i 1.
Four Turbine Throttle valves at least once per 31 days, f
2.
Four Turbine Governor valves at least once per 31 days,
- 3.
Four Turbine Reheat Stop valves at least once per 18 months, and i
4.
Four Turbine Reheat Intercept valves at least once per 18 months.
b.
At least once per 18 months, by performance of CHANNEL CALIBRATION j
l on the turbine overspeed protection instrume its.
c.
At least once per 40 months * *, by disassembly of at least one of each of the above l
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 I
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.
1 Testing of the turbine governor valves may be suspended during end-of-cycle power i
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.
4 NORTH ANNA - UNIT 2 3/4 7-12 Amendment No. 38. S L ! 19.176 1