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Amends 105 & 94 to License DPR-77 & DPR-79,respectively, Changing Tech Specs to Delete Surveillance Requirements for Pressurizer PORVs & Associated Block Valves
	ML20236A668
Person / Time
Site:	Sequoyah
Issue date:	03/09/1989
From:	Black S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20236A670	List: ML20236A668; ML20236A676;
References
	NUDOCS 8903200105
	Download: ML20236A668 (10)
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o UNITED STATES.

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- NUCLEAR REGULATORY COMMISSION 1

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DOCKET NO. 50-327 j

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SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1

4 Amendment No.105 License No. DPR-77

- i 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated December 6, 1988, 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; 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.

There is reasonable assurance (1) that the activities authcrized by j

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

conducted in compliance with the Com.ssion'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 accord?.nce with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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B903200105 890309 i

PDR ADDCK 05000327 P

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

amended to read as follows:

(2) Technical Specifications The. Technical Specifications contained in Appendices A and B, as i

revised through Amendment No.105, 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 T

N S za.n'e lack, Assistant Director or Projects i

TVA Projects Division Office of Nuclear Reactor Regulation i;

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 9, 1989 l

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' ATTACHMENT TO LICENSE AMENDMENT N0. 105 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 i

l l Revise the Appendix A Technical Specifications by removing the pages I

identified'below and inserting the enclosed pages. The revised pages j

are' identified by the captioned amendment number and contain marginal i

lines: indicating the area of change. Overleaf pages* are provided,to j

maintain document completeness.

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

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REACTOR COOLANT SYSTEM RE' LIEF VALVES - OPERATING LIMITING CONDITION FOR OPERATION j

3.4.3.2 Two power relief valves (PORVs) and their associated block valves l

shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

4 1

a.

With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b.

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve (s) to OPERABLE status or close the block 1

1 valve (s) and remove power from the block valve (s); otherwise, 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 COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS I

l 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 l

l b.

by operating the valve through one complete cycle of full travel.

4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

L SEQUOYAH - UNIT 1 3/4 4-4a Amendment No.12,105

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NUCLEAR REGULATORY _ COMMISSION -

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TENNESSEE VALLEY AUTHORITY

'1 DOCKET NO. 50-328 I

1 SEQUOYAH NUCLEAR PLANT, UNIT 2-AMENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No. 94 License No. DPR-79 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated December 6,1988, 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 j

Chapter I; B.

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

previsions cf the Act, 'and the rules and regulations of the Comission;.

C.

There is reasonable. assurance (1) that the activities authorized by this arrendnent car, be conducted without endangering the health anc safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.-

The issuance of tihis amendment will not be inimical to the common defense and security or to the health and-safety of the public; and a.

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 by. changes to the Technical l

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

(2) Technical Specifications s

The Technical Specifications contained in Appendices A and B, as 1

revised through Amendment No. 94, 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.

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FOR THE NUCLEAR REGULATORY COMMISSION i

L M

l b S ra.ne black, Assistant Director or Projects TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical e

Specifications-Date of Issuance:

March 9, 1989

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4.0 CONCLUSION

1 The Comission made a proposed determination that the amendment involves no.

l significant hazards consideration which was published in the Federal Register (54 FR 1025) on January 11, 1989 and consulted with the State of Tennessee.

'No public coments.were received and the State of Tennessee did.not have any coments.

The staff has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such dCtivities will be ConducteG ir, ccmpliance with the Comission's re-gulations, and the issuance of the amendments will-not be inimical to the common defense and security nor to the health and safety of the public.

Principal Contributor:

J. Watt Dated:

March 9, 1989 1

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ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE N0. DPR-79 i

DOCKET NO. 50-328 l

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I Revise the Appendix A Technical Specifications by removing the pages-identified below and inserting the enclosed pages.

The revised pages j

are identified by the captioned amendment number.and contain marginal 1

lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.

PEMOVE INSERT 3/4 4-7 3/4 4-7*

i 3/4 4-8 3/4 4-8 I

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" REACTOR C00LANT' SYSTEM

3/4.4.3. SAFETY AND RELIEF VALVES -1 OPERATING

-SAFETY VALVES'- OPERATING

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LIMITING CONDITION FOR OPERATION

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1q 3.4.3.1:. All-pressurizer code safety valves shall be' 0PERABLE with a lif t:

setting ofL2485 PSIG

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' APPLICABILITY:

MODES 1,.2 and 3.

ACTION:

With one pressurizer c' ode. safety, valve inoperable, either restore the inoperable'

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v'alve-to' OPERABLE status;within.15 minutes or be in'at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in'at least HOT-SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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SURVEILLANCE' REQUIREMENTS qj

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4.4.3.1 'No additional Surveillance. Requirements other than those required.by Specification 4.0.5.'

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The lift setting pressure shall correspond to ambient conditions of the valve at' nominal operating temperature and pressure.

j SEQUOYAH - UNIT-2 3/4 4-7 4

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'g REACTORC00thNTSYSTEM D:

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RELIEF VALVES - OPERATING:

OMITINGCONDITIONFOROPERATION q

q 3.4.3.2 ' All power operated relief: valves (PORVs) and their associated block' valves shall be OPERABLE.

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

g ACTION:

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a.

With one or more p0RV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore-the PORV(s) to OPERABLE status or close.the associate'd-block valve (s)'

and remove power from the block valve (s); otherwise, be in at least 1'

HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the.

following-30 hours.

3 b.

With one or more block-valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either-restore the block valve (s) to OPERABLE status or close.the block.

valve (s).and remove power from the block valve (s); otherwise, be in j

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 COLD:SHUTOOWN.

within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The provisions of. Specification 3.0.'4 are not applicable, c.

4

$ 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

]

b.

Operating'the valve through one complete cycle of full travel, l

l 4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once per 1

92 days by operating the valve through one complete cycle of full travel.

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SEQUOYAH - UNIT 2 3/4 4-8 Amendment No.

94

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ML20236A668

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