ML20058M303
| ML20058M303 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/31/1990 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058M305 | List: |
| References | |
| NUDOCS 9008100042 | |
| Download: ML20058M303 (10) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT N0. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE i
Amendment No. 132 License No. NPF-4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company, etal.,(thelicensee)datedJuly 23, 1990, complies with the stand-ards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and seccarity 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 Comission's regulations and all applicable r, luirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2)TechnicalSpecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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This license erandment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Gus C. Lainas, Assistant Director for Region II Reactors
.o Division of Reactor Projects - I/II Office of Nuclear Reactor, Regulation
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Attachment:
Changes to the Technical Specifications Date of Issuance: July 31, 1990 l,'
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ATTACHMENT TO LICENSE AMrNDMENT NO. 132 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 vertical lines indicating the area of change. The cor-responding overleaf page is also provided to maintain document completeness.
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TABLE 3.3-1 (Continued) h REACTOR TRIP SYSTEM INTERLOCKS 5$
3 ALLOWABLE 3
DESlGNATION CONDITION SETPOINT VALUES FUNCTION-P-7 (Cont'd) 3 of 4 Power range beim 8%
>7%
Prevents reactor trip when g
setpoint any of the following occurn g
and Iow flow, reactor coolant 2 of 2 Turbine Impulse 8%
>7%
pump breakers open, under-chamber pressure below voltage (RCP busses), under-setpoint frequency (RCP busses),
l (Power level decreasing) pressurizer low pressure or pressurizer high level.
P-8 2 of 4 Power range above 30%
<31 %
Allows reactor trip when' any of setroint the following ' occur: clow flow.
wa in a single loop, a single (Power level increasing) reactor coolant pump breaker open, or a turbine trip.
3 of 4 Power range belo'w 28%
>27%
Prevents reattor trip when setpoint any of the following occur:
low flow in a single loop, (Power level decreasing) a single reactor coolant pump'-
breaker open, or a turbine--
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trip.
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REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES
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FUNCTIONAL UNII RESPONSE TIME 5
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1.
Manual Reactor Trip fl0T APPLICABLE 2.
Power Range, Neutron Flux
< 0.5 seconds
- 3.
Power Range, Pautron Flux, High Positive Rate NOT APPLICABLE l
4.
Power Range, Neutrcri Flux, R
High Negative Rate w
1 0.5 seconds
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5.
Intermediate Range, f!cutron Flux NOT APPLICABLE 8
6.
Source Range Neutron 1%:x
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_ 0.5 seconds
- 7.
Overtemperature AT l
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-< 4.0 seconds
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8.
Overpower AT NOT APPLICABLE 2M 9.
Pressurizer Pressure--Low
_ 2.0 seconds 10.
Pressurizer Pressure--High.
< 2.0 seconds E${
- 11. Pressurizer Water level--High' 1 2.0 seconds **
si Neutron detectors are exempt' from response time testing. Response of the neutron flux signal o := i i?
portion of the channel time shall be measured from detector output or input of first electronic Mg component in channel.
- ** Response time testing for " Pressurizer Water Level -- High" shall be. implenented no later than
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startup (entry into Mode 2) for Cycle 9.
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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 Amendment No. 116 License No. NPF-7 1.
The Nuclear Regulatory.Comission (the Comission) has found that:-
A.
The application for amendment by. Virginia Electric and Power Company, etal.,(thelicensee)datedJuly 23, 1990, complies with the stand-ards and requirements.of the Atomic Energy Act of 1954, as cmended (the Act), and the Comission's rules and regulations set forth-in 10 CFR Chapter I;
' B. -The facility will operate in conformity with the application, tt.s provisions of the Act, and the rules and regulations of the Comi>sion; 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
'2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as' indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Specifications.
The Technical Specifications contained in Appendices A and B,in the as revised through Amendment No.
, are hereby incorporated license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is. effective as'of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION:
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/ Gus.C. Lainas Assistent t$ rector for Region II Reactors Division of Reactor Projects - I/II Off_ ice of Nuclear Reactor Regulation
Attachment:
- Changes to the Technical Specifications Date of Issuance:- 0;ly 31,1990 e
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.l ATTACHMENT T0 LICENSE AMENDMENT N0.116
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L TO FACILITY OPERATING LICENSE N0.'NPF,;
J DOCKET NO. 50-339.
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 vertical lines indicating the area of. change. The cor-
' responding overleaf page<1s also provided to maintain dccument'comnleteness.
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~y TABLE 3.3-1 (Continued) 35 REACTOR TRIP SYSTEM INTERLOCKS--
a:
ALLOWABLE-DESIGNATION CONDITION SETPOINT FUNCTION
. VALUES
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P-7 (Cont'd) 3 of 4 Power range below
- 8%
>7%
Prevents reactor trip when any 25 setpoint of the following-occur: -low
-d and flow, reactor coolant pump 2 of 2 Turbine Impulse-8%
>7% -
breakers open, undervoltage
^2 (RCP busses), underfrequency chr ber pressure below.
(RCP busses), pressurizerL setpoint (Power level decreasing) low pressure ~or pressurizer high level.
-s P-8 2 of 4 Power range above 30%-
<31%
Allows eactor trip wh'en any setpoint of the following occur:- low flow in a single loop,'a single (Power level increasing) reactor coolant pump breaker open, or a turbine trip."
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3 of 4 Power range below 28%
>27%
Prevents reactor trip when any_
setpoint-of the following occur: low
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flow in a single loop, a single (Power level decreasing) reactor coolant pump breaker' open, or a. turbine trip.
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TABLE'3.3-2 5
fl REACTOR TRIP SYSTEN INSTRUNENTATION RESPONSE TINES 1
E E
FUNCTIONAL-UNIT RESPONSE TINE.
h 1.
Manual Reactor Trip-NOT APPLICABLE i'i
{l 2.
Power Range, Neutron Flux 5 0.5 seconds
- 3.
Power Range, Neutron Flux, High Positive Rate NOT APPLICABLE 4.
Power Range, Neutron Flux, High Negative Rate
< 0.5 seconds
- 5.
Intermediate Range, Neutron Flux NOT APPLICABLE 6.
Source Range, Neutron Flux 7:_ 0.5 seconds
- 7.
Overtemperature AT
$ 4.0 seconds
- 8.
Overpower AT NOT APPLICABLE 9.
Pressurizer Pressure--Low
<'2.6 s conds 10.
Pressurizer Pressure--High
$ 2.0 seconds n,
4 F;
- 11. Pressurizer Water Level--High lE ?E
--< 2.0 seconds **
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8 & Neutron detectors are exempt-from response time testing.
Response of the neutron flux signal G@ portion of the channel time shall be measured from detector output or input of first electronic component in channel.
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- Response time testing for " Pressurizer Water Level -- High" shall be implemented no later than startup l
0$ 23 (entry into Mode 2) for Cycle 8 o-
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