ML20043H583

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Amends 56 & 48 to Licenses DPR-77 & DPR-79,respectively, Correcting Line Item Alignment
ML20043H583
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 07/20/1987
From: Zwolinski J
NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20043H581 List:
References
NUDOCS 9006260139
Download: ML20043H583 (8)


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UNITED STATES

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nf NUCLEAR REGULATORY COMMISSION 3,., r 3

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f TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327

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SEQUOYAH NUCLEAR PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. DPR-77 1.

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

A.

'The application for amendment by Tennessee Valley Authority' (the licensee) dated April 16, 1987, 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 l.

Chapter I; l

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B..

The facility will operate in conformity with the application.the provisions of the Act, and the rules and regulations of the I

' Comission; There is reasonable assurance (1) that the activities authorized by C.

this amendment can be conducted without endangering the health and-l 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 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.

9006260139 870720 DR ADOCK 0500 7

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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. 56, 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.

f FOR THE NUCLEAR REGULATORY-OMMISSION 1

1 John

. Zwolinski, Assistant Director-for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications i

Date of Issuance: July 20, 1987 4

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l ATTACHMENT TO LICENSE AMENDMENT NO. Es FACILITY OPERATING LICENSE NO. DPR-77 1

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DOCKET NO. 50-327 i

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

identified below and inserting the enclosed pages. The. revised pages I

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 3-3 3/4 3-3*

3/4 3-4 3/4 3-4 1

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' REACTOR TRIP SYSTEM INSTRUMENTATION

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MINIMUM-c TOTAL 'AD.

CHANNELS' CHANNELS APPLICABLE

] FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES-ACTION 12.

Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7

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(Above P-8) any oper-each oper-ating loop ating loop 13.

Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop 1

7 (Above P-7 and below P-8) two oper-each oper- -

ating loops ating loop i

14. Main Steam Generator 3/ loop 2/ loop in 2/ loop in 1, 2 7

Water Level--Low-Low any oper-each oper-y ating loop ating loop j

T 15.

Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/ loop-1, 2 7

Mismatch and Low Steam and coincident level and i

Generator Water Level 2/ loop-flow with 2/ loop-flow

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mismatch in 1/ loop-flow mismatch or

.scue loop mismatch in 2/ loop-level same loop and 1/ loop-flow mismatch

16. Undervoltage-Reactor Coolant l

Pumps 4-1/ bus 2

3 1

6,

17. Underfrequency-Reactor. Coolant g

Pumps 4-1/ bus 2

3 1

6 18.- Turbine Trip A.

Low Fluid Oil Pressure 3

2 2

7, 8.

-Turbine Stop Valve Closure.

4 4

4 1

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- ! 't c NUCLEAR REGULATORY COMMISSION WASHINGTON D.C.20666 O

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0VOYAH NUCLEAR PLANT, UNIT 2 l

AMENDMENT TO FACILITY OPERATING LICENSE

-1 Amendment No.48 I

License No. DPR-79

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.1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee)datedApril 16, 1987, complies with the standards and L

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

1 and the.Comission's rules and regulations set forth,in 10 CFR Chapter I;.

l B.

The facility will operate in conformity with the application, the provisions of the Act, and the' rules and regulations of the I

' Comission; -

'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-e conducted in compliance with the Comission's regulations; i-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 i

E.

The issuance of this snendment is 'in accordance with 10 CFR Part 51 of the Commissier.'s regulations and all applicable requirements have 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 and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:

(2)'TechnicalSpecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 48 ', are hereby incorporated in the i

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.

i FOR THE NUCLEAR REGULA ORY,00MMISS10N w

Joh A. Zwolinski, Assistant' Director 1

fo Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical l.

Specifications Date of Issuance: July 20, 1987 L

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ATTACHMENT TO LICENSE AMEN 0 MENT NO. ao FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-323 Reviss the Appendix 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, j

REMOVE INSERT 3/4 3-3 3/4 3-3*

1 3/4 3-4 3/4 3-4 9

.1 j

l l

s TABLE 3.3-1-(Continued) 2 u.

'c">

8 REACTOR TRIP SYSTEN INSTRUMENTATION II MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE E-FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MOOLS ACTION Z

s 12.

Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7 u

(Above P-8) any oper-each oper-ating loop ating loop 13.

Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop.

I 7

(Above P-7 and below P-8) two oper-each oper-ating loops' ating loop 14.

Steam Generator Water 3/ loop 2/ loop in 2/ loop in 1, 2 7

Level--Low-Low any oper-each oper-ating loops ating loop w

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Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/ loop-level 1, 2 7

J, Mismatch and Low Steam and coincident and y

Generator Water Level 2/ loop-flow with 2/ loop-flow mismatch in 1/ loop-flow misaatch'in same loop mismatch in same loop or same loop 2/ loop-level and 1/ loop-flow mismatch in same loop 16.

Undervoltage-Reactor Coolant 4-1/ bus 2

3 1

6 Pumps 9

17. Underfrequency-Reactor Coolant 4-1/ bus 2

3 1

6 Pumps

18. Turbine Trip A.

Low Fluid Oil Pressure 3

2 2

1 7

B.

Turbine Stop Valve Closure 4

4 4

I 13,

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