Text

Amends 124 & 113 to Licenses DPR-77 & DPR-79,respectively, Temporarily Adding Two Addl Action Statements for Limiting Condition for Operation 3.5.1.1
	ML20245L822
Person / Time
Site:	Sequoyah
Issue date:	08/11/1989
From:	Liaw B; Office of Nuclear Reactor Regulation
To:	;
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ML20246A001	List: ML20245L822; ML20246A003;
References
	NUDOCS 8908220329
	Download: ML20245L822 (10)
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendirent No.124 Licerse No. DPR-77 I

1.

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

A.

The applications for amenoment by Tennessee Yelley Authority (the licensee) dated August 7, 1989, as revised August 10, 1989, 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; U.

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 (i) that the activities authorized by

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this amendment can be conducted without endangering the health and i

safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;

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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 E.

The issuance of this amendment is in accordance with 10 CFR Part 51 i

of the Commission's regulations and all applicable requirements have l

been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment i

and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby

. amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.124, 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.

FOR THE NUCLEAR REGULATORY CCMMISSION 0g L k.13aw, Directorv TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 11, 1989

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ATTACHMENT TO LICENSE AMENDMENT NO.124 FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327

. Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages dre identified by the Captioned amendment number and Contain marginal lines indicating the area of change.

Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT 3/4 5-1 3/4 5-1 3/4 5-2 3/4 5-2 i

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3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) i o

F 3/4.5.1 ACCUMULATORS

' COLD LEG INJECTION ACCUMULATORS

. LIMITING CONDITION FOR OPERATION 3.5.11 Each cold leg injection accumulator shall be OPERABLE with:

The isolation valve'open, a.

- b.

A contained borated water volume of between 7857 and 8071 gallons of-l borated water, Betweea 1900 and 2100 ppm of boron, and c.

d.

A nitrogen cover pressure of between 385 and 447 psig.

APPLICABILITY:

MODES 1, 2 and 3.*

ACTION:

With one cold-leg. injection accumulator inoperable, except as a result a.

of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within one hour or be in at least HOT STANDBY the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one cold leg injection accumulator inoperable due to the isola-tion valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With cne pressure or water level channel inoperable per accumulator, c.

return the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d. #

With more than one channel (pressure or water level) inoperable per accumulator, immediately declare the affected accumulator (s) inopercble.

Pressurizer pressure above 1000 psig.

-# Actions c and d are in effect until the restart of Unit 2 from the Unit 2 Cycle 4 refueling outage.

SEQUDYAH - UNIT 1 3/4 5-1 Amendment No. 124

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e EMERGENCY CORE COOLING SYSTEMS (ECCS) 5 SURVEILLANCE' REQUIREMENTS-o' 1

<4.5.1.1.1 Each cold leg injection accumulator shall be demonstrated OPERABLE:

la.

At least'once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1.

-Verifying, by the absence of alarms or by measurement of levels and pressures, the contained borated water volume and nitrogen coser pressure in the tanks, and 2.-

Verifying that each cold leg injection accumulator isolation valve is open.

b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of~ greater than or equal to 1% of tank volume by verifying the boron concentration of the cold leg injection accumulator solution.

At least once per 31 days when the RCS pressure is.above 2000 psig-c; by verifying that power to the isolation valve operator is disconnected-by removal of the breaker from the circuit.

d.

At least once per 18 months by-verifying that each cold leg injection accumulator isolation valve opens automatically under each of the following conditions:

1.

When an_ actual or a simulated RCS pressure signal exceeds the P-11 (Pressurizer Pressure Block of Safety Injection) setpoint, 2.

Upon receipt of a safety injection test signal.

4.5.1.1.2 Each accumt

.or water level and pressure channel-shall be demonstrated OPERABLE:

At least once per 31 days by the performance of a CHANNEL FUNCTIONAL a.

TEST.

t.

At least once per 18 months by the performance of a CHANNEL CALIBRATION.

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,.. t SEQUOYAH - UNIT 1 3/4 5-2 Amendment No. 12.124

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WASHINGTON, D. C. 20555

x TENNESSEE VALLEY AUTHORITY-

' DOCKET NO. 50-328 SE000YA8 duCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 113 License No. DPR-79 1

1.-

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

A

'A.-

The applications for amendment by Tennessee t/ alley Authority (the licensee) dated August 7. 1989, as revised August.10,~1989,: complies with the standards 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 L

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 ints;ical to the comon 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.

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2.

Accordingly, the license is amended hy changes to the Technical Specifications as indicated in the. attachment to this license amendment h

and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amenced to read as follows:

(2). Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.113, 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.

FOR THE NUCLEAR REGULATORY COMMISSION l

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. D.

aw, Director T

Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 11, 1989

ATTACHMENT TO LICENSE AMENDMENT NO.113 FACILITY OPERATING LICENSE NO. DPR-79

_ DOCKET NO. 50-328 Revise the Apper: dix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages

~.are identified by the captioned amendment number and contain marginal lines. indicating the area of change.

Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT 3/4 5-1 3/4 5-1 L

3/4 5-2 3/4 5-2 I

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w 3/4.5. EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ' ACCUMULATORS-COLD LEG INJECTION ACCUMULATORS-LIMITING CONDITION FOR'0PERATION-3.5.1.1 Each cold leg injection accuinulator shall be OPERABLE with:

The isolation valve open, a.-

b.

. borated water,A contained borated water volume of between 7857 a Between :1900 and 2100 ppm of boron, and-c.

d.

A nitrogen cover pressure of between 385 and 447 psig.

APPLICABILITY:

MODES 1,-2 and 3.*

ACTION:

'With one cold leg injection accumulator inoperable, except as a a.

result of. a closed isolation valve, restore the inoperable accumulator to OPERABLE status within one hour or be in at le STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN wit following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one cold leg injection accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT S within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. #

With one pressure or water level channel inoperable per accumulator be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months a SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d. # With more than one channel (pressure or water level) inoperable per accumulator, immediately declare the affected accumulator (s) inoperable.

" Pressurizer pressure above 1000 psig.

Actions c and d are in effect until the restart of Unit 2 from the U

-Cycle'4 refueling outage.

1' SEQUOYAH - UNIT 2 3/4 5-1 Amendment No. 113

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. EMERGENCY CORE COOLING SYSTEMS-4 SURVEILf.ANCE REQUIREMENTS 1

4.5, bl.1 Each cold leg injection accumulator shall be demonstrated OPERABLE As: least 'once per 12. hours by:

a.

1.

Verifying, by. the absence of alarms or by measurement of levels and pressures, the. contained borated: water volume and nitrogen L

cover pressure in the tanks, and 2.

Verifying that.each~ cold leg injection accumulator isolation.

valve is open.

b.

At-least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume-increase of greater than or equal to 1% of tank volume by verifying..the boron concentration of the cold leg injection accumulator solution.

'At least once per 31 days when the RCS pressure is above 2000 psig c.

by verifying that power to the isolation valve operator is l

. disconnected by removal of the breaker.from the circuit.

' d.

At._least once.per;18 months by verifying that each cold leg injection accumulator isolation valve opens automatically under each of the

'following~ conditions:

1..

When an actual or a simulated RCS pressure signal exceeds the P-11 (Pressurizer Pressure Block of Safety injection) setpoint, 2

Upon~ receipt of a safety injection-test signal.

4.5.1.1.2 Each accumulator water level and pressure channel shall be demonstrated OPERABLE:

i At least once per 31 days by the performance of a eHANNEL FUNCTIONAL

.a.

TEST.

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b.

At least once per 18 months by the performance of a CHANNEL

'J CALIBRATION.

SEQUDYAH - UNIT 2 3/4 5-2 Amendment No.113 l

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ML20245L822

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