ML20248K314

Amends 110 & 100 to Licenses DPR-77 & DPR-79,respectively, Revising Surveillance Requirements for Electrical Equipment Protective Devices in Plant Units 1 & 2 Tech Specs

ML20248K314
Person / Time
Site:	Sequoyah
Issue date:	04/03/1989
From:	Black S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248K318	List: ML20248K314 ML20248K321
References
NUDOCS 8904170292
Download: ML20248K314 (10)

Text

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NUCLEAR REGULATORY COMMISSION 3

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 d

j-AMENDMENT TO FACILITY OPE, RATING LICENSE Amendment No.110 License No. DPR-77 1.

The Nuclear Regulatory Consnission (the Commission) has found thati A.

The application for amendment by Tennessee Valley Authority (tta f

licensee) dated August 8, 1986, complies 1with the standards and.

requirements of the Atomic Energy Act of 1954, as amended (the Act)..

I and the Consnission's rules and regulativ:>s set forth in 10 CFR Chapter I;

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B.

The facility will operate in conformity with the application, the j

provisions of the Act, and the rules and regulations of the

-l Commission; j

t-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 .;uance 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 i

of the Cossnission's regulations and all applicable requirements have

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been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications es indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No.'0PR-77 is hereby amended to read'as follows:

f (2) Technical Specifications' The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.110, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

l 3.

This license amendment is effective as'of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Suzann k Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 3, 1989 i

_______e

t ATTACHMENT TO LICENSE AMENDMENT NO. 110 1

FACILITY OPERATING LICENSE NO. DPR-77 DOCKET N0. 50-327 Revise the Appendix A Tech'nical 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 i

lines indicating the area of change.

Overleaf pages* are provided to

,i maintain document' completeness.

I REMOVE

. INSERT 3/e 8-15 3/4 8-15 3/4 8-16 3/4 8-16 I

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l ELECTRICAL POWER SYSTEMS l

3/4.'8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES

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CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.1 All-containment penetration conductor overcurrent protective devices specified in appropriate plant instructions shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one or more of the containment penetration conductor overcurrent protecti" devices specified in appropriate plant instructions inoperable:

Restore the protective device (s) to OPERABLE status or de-energize the a.

circuit (s) by tripping the associated backup circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the backup circuit breaker to be tripped at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup _ circuit breakers tripped, or b.

Be in at least H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.8.3.1 All containment penetration conductor overcurrent protective devices specified in appropriate plant instructions shall be demonstrated OPERABLE:

a.

At least once per 18 months:

1.

For at least one 6.9 kV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per 72 months, by performance of:

l (a) A CHANNEL CALIBRATION of the associated protective relays I

l l

specified in appropriate plant instructions, and l

(b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each i

relay and associated circuit breakers and control circuits I

function as designed.

1 SEQUOYAH - UNIT 1 3/4 8-15 Amendment No. 42,110

l ELECTRICAL POWER SYSTEMS 1

SURVEILLANCE REQUIREMENTS (Continued)

(c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 1 of the circuit breekers of the inoperable type shall-also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

l 2.

By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.

Circuit breakers selected for fun:tional testing shall be selected on a rotating basis.

The functional test shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.

Circuit breakers found inoperable during functional testing shall be restored 1

to OPERABLE status prior to resuming operation.

For each circuit breaker found inoperable during these functional tests an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found'or all circuit breakers of that type have been functionally tested.

3.

By selecting and verifying a representative sample of each type of fuse on a rotating basis.

Verification will be accomplished as described by SR 4.8.3.1.a.3.a.

Each representative sample of fuses shall include at least 10% of all fuses of that type.

A complete listing of all fuses to be verified in accordance with this requirement will be maintained in appropriate plant instructions.

Fuses found inoperable during verification shall be replaced with OPERABLE fuses prior to resuming operation.

For each fuse found inoperable during verification, an additional representative sample of at least 10% of all fuses of that type shall be functionally i

tested until no more failures are found or all fuses of that type have been functionally tested.

1 (a) A fuse verification and maintenance program will be maintained to ensure that:

1.

The proper size and type of fuse is installed, 2.

The fuse shows no sign of deterioration, and 3.

The fuse connections are tight and clean.

b.

At least once per 60 months by subjecting each circuit breaker to an i

inspection and preventive maintenance in accordance with appropriate l

plant instructions based on manufacturer's recommendations.

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SEQUOYAH - UNIT 1 3/4 8-16 Amendment No. 44 110 (Corrected page)

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UNITED STATES

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WASHINGTON. O, C. 20655 k

g TENNESSEE VALLEY AUTHORITY A

DOCKET NO. 50-328 l

SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE j

Amendment No.100 License No. OPR-79 l

1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 8, 1986, complies with the standards and requirements of the Atomic' Energy Act of 1954, as amended (the Act),

i and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the 3

provisions of the Act, and the rules and regulations of the i

Comissicn; C.

There is rtasonable assurance (i) that the activities authorized by 3

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i

conducted in compliance with the Comission'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 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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-l 2.

Accordingly, theilicense is amended by changes to the Technical

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f Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as.follows:

.j (2) Technical Specifications j

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.100, are hereby incorporated in the 4

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 Suzanne lack, Assistant Director for Projects I

TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issue.nce: April 3, 1989 I

i

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ATTACHMENT TO LICENSE AMENDMENT NO. 100 FACILITY OPERATING LICENSE NO. DPR-79 00CKET NO. 50-328 1l Revise the Appendix A Technical Specifications by removing the pages

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identified belowland inserting the. enclosed pages.

The revised pages

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

Overleaf pages* are provided to maintain document completeness.

l l

REMOVE INSERT 3/4 8-16 3/4 8-16 3/4 8-17 3/4 8-17 I

l

i 1

ELECTRICAL POWER SYSTEMS 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 1

i LIMITING CONDITION FOR OPERATION 3.8.3.1 All containment penetration conductor overcurrent protective devices specified in appropriate plant instructions shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one or more of the containment penetration conductor overcurrent protective devices specified in appropriate plant instructions inoperable:

Restore the protective device (s) to OPERABLE status or de energize the a.

circuit (s) by tripping the associated backup circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the backup circuit breaker to be tripped at least l

once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, or b.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS l

l 4.8.3.1 All containment penetration conductor overcurrent protective devices j

specified in appropriate plant instructions shall be demonstrated OPERABLE:

q a.

At least once per 18 months.

1.

For at least one 6.9 kV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per 72 months, by performance of:

(a) A CHANNEL CALIBRATION of the associated protect."e relays specified in appropriate plant instructions, an (b) An integrated system functional test which incluo.s simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.

l SEQUOYAH - UNIT 2 3/4 8-16 Amendment No. 34, 100

1 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

(c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 1 of the curcuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

l 2.

By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.

Circuit breakers selected for functional testing shall be selected on a rotating basis.

The functional test shall consist of injecting a l

current input at the-specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.

Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.

For each circuit breaker found inoperable during these functional tests, an additional representati.ve sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

3.

By selecting and verifying a representative sample of each type of fuse on a rotating basis.

Verification will be accomplished as described by SR 4.8.3.1.a.3.a.

Each representative sample of fuses-shall include at least 10% of all fuses of that type. - A complete listing of all fuses to be verified in accordance with this require-ment will be maintained in appropriate plant instructions.

Fuses found inoperable during verification shall be replaced with OPERABLE fuses prior to resuming operation.

For each fuse found inoperable during verification, an additional representative sample of at least 10% of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.

(a) A fuse verification and maintenance program will be maintained to ensure that:

1 1.

the proper size and type of fuse is installed, 2.

the fuse shows no sign of deterioration, and l

3.

the fuse connections are tight and clean, b.

At least once per 60 months by subjecting each circuit breaker to an in-spection and preventive maintenance in accordance with appropriate plant instructions based on manufacturer's recommendations.

1 I

SEQUOYAH - UNIT 2 3/4 8-17 Amendment No. 34, 100 (Corrected page) o7-M O - N

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