Text

Amends 60 & 44 to Licenses NPF-4 & NPF-7,respectively, Changing Tech Specs by Revising P-7 Reactor Trip Sys Interlock Setpoint to Indicate Pressure Equivalent to 10% Rated Turbine Power
	ML20101P325
Person / Time
Site:	North Anna
Issue date:	12/06/1984
From:	John Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20101P328	List: ML20101P325; ML20101P330;
References
	NUDOCS 8501070114
	Download: ML20101P325 (10)
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UNITED STATES NUCLEAR REGULATORY COMMISSION o

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WASHINGTON, D. C. 20555 A...../

VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERAT'ING LICENSE Amendment No.60 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

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(the licensee) dated December 30, 1983 as supplemented June 4, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regula-tions set forth in 10 CFR Chapter I; 7

B. ' The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission;

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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 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.

8501070114 841206 PDR ADOCK 05000 P.

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Accordin' gly, the li' cense is amended by changes to the Technical Spect-fications as indicated in the attachment to this license amendment, and paragraph _2.C.(2) of Facility Operating License No. NPF-4 1s hereby anended to read as follows:

v (2) Technical S'pecifications The Technical Specifications contained in Appendices A and B, as resised through Amendment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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This license amendment is effective asi of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION c

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James R. Miller, Chief 7

Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 6,1984

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.60 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 pf change.

The corresponding overleaf page is also provided to maintain document completeness.

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TABLE 3.3-1 (Continued) 2 B

M REACTOR TRIP SYSTEM INTERLOCKS 2

E ALLOWABLE

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DESIGNATION CONDITION SETPOINT VALUES FUNCTION

-10

'P-6 1 of 2 Intermediate range 1 x 10

<3 x 10 Allows manual block of above setpoint (increasing source range reactor tr.ip m

power level)

-II

-II 2 of 2 Intermediate range 5 x 10

> 3 x 10 Defeats the block of source below setpoint (decreasing range reactor trip power level)

P-10 2 of 4 Power range above set-10%

<11%

Allows manual block of power R

point (increasing power level)

. range (low setpoint) and inter-mediate range reactor trips and Y

intermediate range rod stop.

Blocks source range reactor trip.

3 of 4 Power range below set-8%

>7%

Defeats the block of power point (decreasing power level) range (low setpoint) and inter-

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mediate range reactor trips and g

intermediate range rod stop.

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Input to P-7.

5 P-7 2 of 4 Power range above set-10%

<11%

Allows reactor trip on:

Low point flow or reactor coolant pump

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or breakers open in more than one 1 of 2 Turbine Impulse Pressure equiv-

<l1%

loop, Undervoltage (RCP busses) g chamber pressure above i alept.to 10%

Underfrequency (RCP busses),

setpoint rated turbine Turbine Trip, Pressurizer lo,y power pressure, and Pressurizer high level.

(Power level increasing) t

71 TABLE 3.3-1 (Continued)

ACTION 9 -

' With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for. up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.l;l.

ACTION 10 -

With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below P-8 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Operation below P-8 may continue pursuant to_ ACTION 11.

ACTION 11 -

With less'than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 -

With the number of channels OPERABLE one less than re-quired by the Minimum Channels OPERABLE requirement, restore the inoperable channel to 0.PERABLE status within

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48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY with~in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

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VIRGINIA ELECTRIC AND POWER COMPANY l

l OLD DOMINION ELECTRIC COOPERATIVE l

DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.44 License No. NPF-7 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Virginih' Electric and Power Company (the licensee) dated December 30, 1983 as supplemented June 4,1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regula-tions 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 (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.

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... 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 The Technical Specifications contained in Appendices A.and B, as revised through Amendment No. 44, 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 the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/

dames R. Miller, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 6, 1984 9

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t-W ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0.44 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 compl.eteness.

Page i

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TABLE 3.3-1 (Continued)

ACTION 9 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance tasting pe~r Specification 4.3.1.1.1.

ACTION 10 - With one channel inoperable, restord the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below the P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant Pump. Breaker Position) setpoint, within the hext 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

l Operation below the P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, may continue pursuant to ACTION 11.

l ACTION 11 - With less than the flinimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

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NORTil ANNA - UNIT 2 3/4 3-7

TABLE 3.3-1 (Continued)

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REACTOR TRIP SYSTEM INTERLOCKS ALLOWABLE P

DESIGNATION CONDITION SETPOINT VALUES FU'!CTION

-10

-10 P-6 1 of 2 Intermediate range 1 x 10

< 3 x 10 Allows manual block of.

above setpoint (increasing source rainge reactor trip m

power level)

-II 2 of 2 Intermediate range 5 x 10

> 3 x 10-II Defeats the block of source below setpoint (decreasing range reactor trip power level)

P-10 2 of 4 Power range above set-10%

<l1%

Allows manual block of power.

E' point (increasing power level) range (low setpoint) and inter-

^

mediate range reactor trips and,

Y intermediate range rod stop..

Blocks source range reactor trip.

3 of 4 Power range below set-8%

> 7%

Defeats the block of power point (decreasing power level) range (low setpoint) and inter-

')

mediate range reactor trips and p

intermediate range rod stop.

8 R

Input to P-7.

8 P-7 2 of 4 Power range above set-10%

<l1%

Allows reactor trip on: Low point flow or reactor coolant pump 2

P or breakers open in more than one 1 of 2 Turbine Impulse Pressure equiv-

<l1%

loop, Undervoltage (RCP busses) u" chamber pressure above alqnt.to 10%

Underfrequency (RCP busses),

i setpoint rated turbine

. Turbine Trip, Pressurizer 16w power pressure, and Pressurizer high level.

(Power level increasing)

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ML20101P325

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