ML20056H632
| ML20056H632 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/30/1993 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056H633 | List: |
| References | |
| NUDOCS 9309100236 | |
| Download: ML20056H632 (7) | |
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UNITED STATES i sd ~
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NUCLEAR PEGULATORY COMMISSION q
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l VIRGINIA ELECTRIC AND POWER COMPANY j
l OLD DOMINION ELECTRIC COOPERATIVE 1
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DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.152 License No. NPF-7 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power l
Company, et al., (the licensee) dated December 4.1992, 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; l
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; i
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.
9309100236 930830 PDR ADOCK 05000339 P
PDR I
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 Specifications j
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 152, 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
/
H ert N. Berko, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance: August 30, 1993 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 152 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by l
amendment number and contain vertical lines indicating the area of change.
j The corresponding overleaf pages are also provided to maintain document completeness.
i Remove Paaes Insert Paoes 2-6 2-6 3/4 2-16 3/4 2-16 l
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SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The reactor trip system instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
APPLICABILITY: As shown for each channel in Table 3.3-1.
ACTION:
With a reactor trip system instrumentation setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
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l NORTH ANNA - UNIT 2 2-5
- l l
x TABLE 2 2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS l
FLNCTIONALUNIT TRIP SETPOINT Al I OWABLE VALUES 4
-e N
1.
Manual Reactor Trip Not Applicable Not applicable l
2.
Power Range, Neutron Flux Low Setpoint - s 25% of RATED Low Setpoint - s 26% of RATED THERMALPOWER THERMALPOWER High Selpoint - s 109% of RATED High Setpoint - s 110% of RATED THEFIMALPOWER THERMALPOWER J
3.
Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 5.5% of RATED THERMAL POWER s
High Positive Rate a time constant 2 2 seconds with a time constant 2 2 seconds
-4.
Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 5.5% of RATED THERMAL POWER Hi h Negative Rate a time constant 2 2 seconds with a time constant 2 2 seconds D
5.
Intermediate Range, Neutron s 25% of RATED THERMAL POWER 530% of RATED THERMAL POWER Flux 6.
Source Range, Neutron Flux s 105 counts per second s 1.3 x 105 counts per second 7.
Overtemperature AT See Note 1 SeeIJote 3 i
8.
Overpower AT See Note 2 See Note 3 l
9.
Pressurizer Pressure--Low 21870 psig 21860 psig
- 10. Pressurizer Pressure--High 5 2385 psig
$ 2395 psig
- 11. Pressurizer Water Level-High 5 92% of instrument span s 93% of instrument span r
- 12. Loss of Flow 2 90% of design flow per loop
- 2 89% of design flow per loop *
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' Design flow per loop is one-third of the minimum allowable Reactor Coolant System Total Flow Rate as specified in Table 3.21.
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POWER DISTRIBUTION LIMITS ONS PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNS related parameters shall be maintained within the limits shown on Table 3.2-1:
Reactor Coolant System T,yg i
a.
i b.
Pressurizer Pressure l
c.
Reactor Coolant System Total Flow Rate i
APPLICA8ILITY: MODE 1 l
ACTION:
With any of the above p6rameters exceeding its limit, restore the parameter to+
within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than SE of i
RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREENTS j
4.2.5.1 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least orce per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.2.5.2 The Reactor Coolant System total flow rate shall be detemined to be within its lielt by measurement at least once per 18 months.
NORTH ANNA - UNIT 2
,3/4 2-15 l
5 mM TABLE 3.2-1 li i
Z DM3 PARAMETERS ro i
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LIMITS 2 Loops in Operation" 2 Loops in Operation" 3 Loops in
& Loop Stop
& Isolated Loop PARAMETER Operation Valves Onen Ston Valves Closed e
Reactor Coolant System Tavg s 591*F g
Pressurizer Pressure 2 2205 psig*
y Reactor Coolant System 2 275,300 gpm g
Total Flow Rate
- Limit not apphcable 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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