ML20198P905

Amend 230 to License DPR-77,revising TS SR 4.4.3.2.1.b for Remainder of Cycle 9 to Perform Stroke Testing of power-operated Relief Valves in Mode 5 Rather than Mode 4

ML20198P905
Person / Time
Site:	Sequoyah
Issue date:	01/13/1998
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198P911	List: ML20198P905 ML20198P917
References
NUDOCS 9801220290
Download: ML20198P905 (4)

Text

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UNITED STATES

-. g lj NUCLEAR REGULATORY COMMISSION f

WASHINGTON, c.C. 30eeH001

\\.....**

TENNESSEE val i FY AUTHORITY -

DOCKET NO. 50-327 SEQUOYAH NUCl FAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 230 License No. DPR-77

1. The Nuclear Regulatory Commission (the Ce mmission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated November 21,1997, 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; 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; 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.

9901220290 990113 PDR ADOCK 05000327 P

PDR

2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment. 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. 230, 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, to be implemented no later than 45 days of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L

Frederick J. Hebddn, Director Project Directorate 11-3 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation

Attachment:

1. Changes to the Technical Specifications Date ofissuance: January 13, 1998 l

l l

i

l ATTACHMENT TO LICENSE AMENDMENT NO. 230 FACIL?TY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised pages are identifed by the captioned amendment number an,'.ontain marginallines indicating the area of change.

REMOVE INSERT 3/4 4-4a 3/4 4-4a

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t'

_ i REACTOR COOLANT SYSTEM r

RELIEF VALVES - OPERATING

- LIMITING CONDITION - FOR OPERATION 3.4.3.2 _Two power relief valves-(PORVs)[and their associated block valves.

~_

1 shall be OPERABLE.

R16 --

APPLICABILITY:- MODES 1, 2,:and 3.

Ellatl8 h

a.;

= With one or more PORV(s) inoperable, but capable of RCS pressure R115 control, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE-

=:tatus or close the associated block valve (s); otherwise, be in at -

least NOT STANDBY witrin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in NOT SHUTDOWN

-lR161 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With one PORV inoperable and incapable of RCS pressure control,_

b.

- within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close:

R115' the associated block valve and remove power from the block valves a

restore the PORV to OPERABLE status within_the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 HOT SHUTDOWN-R161 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, With both'PORVs inoperable and incapable of RCS pressure control, c.

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore each of the PORVs to OPERABLE status R115 or close their associated block valves and remove power from the block valves and be in 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 NOT R161

~

i SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

d..

. With one or more block valve (s) inoperable, with!n 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (1) restore the block valve (s) to OPERABLE status, or close the block R115 valve (s) sad remove power from the block valve (s), or close the~

PORV (s) and remove power from its attaciated solenoid valve (s); and (2) apply the ACTION b. or c. above, as appropriate, for the isolated PORV(s).

The provisions of Specification 3.0.4 are not applicable, e.

SURVEILLANCE REQUIREMENTS 4.4.3.2.1 In addition to the requirements of Specification 4.0.5, each PORV

-shall be demonstrated OPERABLE at least once per 18 months by:

a.-

Performance of~a CHANNEL CALIBRATION, and h.

Operating the valve through one complete cycle of full travel lR161

-during mode 4.*

.l 4.4.3.2.2-Each block-valve shall be demonstrated CP:RABLE at'least once per 92 days by-operating the valve through one complete cycle of full travel.

• -For Unit =1' Cycle 9 operation only, this surveillance may be met by testing in Mode 5 with the pressuriser in saturated condition and temperature greater

than or' equal to 420' degrees Fahrenheit. Any entry into Mode 4-during Unit 1 iCycleLS. operation will require performance of this surveillance in this mode.

SEQUOYAN S UNIT 1

_3/4 4 4a Amendment Nos. 12, 105, 111, if7, AM2GHENT NO. 230 L

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