ML20043H810

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Corrected Amend 141 Amend to License DPR-77,providing Revised Tech Spec Pages Re Reactor Trip Sys Instrumentation Trip Setpoints
ML20043H810
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 05/16/1990
From: Black S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20043H811 List:
References
NUDOCS 9006260474
Download: ML20043H810 (4)


Text

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UNITED STATES i

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NUCLEAR REGULATORY COMMISSION g.

t W ASHING TON, D. C. 20bS5 TENNESSEEVALLEY.AlfTHpjlTY, DOCKETNO.50.}jl SEQUOYAH NUCMAjj)f}!,T,.l!N,1,T,.}

3 ANEkDNENT.TO.rACIkJTLOPERATlWGLICENSE Anendrent ilo.141 License No. DPR-77 j

2 1.

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

J A.

The application for amendir4.nt by Tennessee Valley Authority (the i

licensee) dated January 24 April 25, and May 15, 1990, conplies with the standards and requirements of the Atomic Energy Act of 1954, as aunded (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; D.

The facility will operate in cerformity with the application, the provisions of the Act, and the rules and regulations of the i

Comissien;

]

1 C.

Thereisreasonableassurance(i)thattheactivitieseuthorizedby i

this arr.er.dr.ent can be cenducted without endai.gering the health ano safety of the public, and (ii) that such activities will be conducted in coinpliance with the Comission's regulations; D.

The issuance of this mondment will ret be ir, finical to the corron defense and security or to the health erid se'ety of the public; and E.

The issuance of this ertndirent is in cccoroar ce with 10 CFR Part 51 of the Ccmission's regulations ard all applfcable requirements Frye bur. satit ficc'.

9006260474 900620 PDR ADOCK 05000327 P

PDC

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i C00RECTED PAGES g g TY OrERATING L,1CJ g.N0. 0FR.77 l

DOCKET N0.50 327 4

1 Revised the Appendix A Technic 61 Specifications by renoving the pages i

icentified below ar.c it;serting the erclosed pages. The revised pages 6te ictritifitd by the captict:Lc er:tridnent nurber ar.d colit61r rrargin line iticicating the arca of change.

REMOVE INSERT 2-9 2-9 5-y e

1

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+

d' 2.

Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachnent to this license anendment and paragraph 2.C.(2) of Fecility 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. 141, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendnent is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION tA Suzann Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 16, 1990 l

~

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b TABLE 2.2-1 (Continued) mE8 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS Y

c NOTATION (Continued)

E NOTE 1:

(Continued)

Z (ii) for each percent that the magnitude of (q 9 ) exceeds -29 percent, the AT trip set-g t

b point shall be automatically reduced by 1.50 percent of its value at RATED THERMAL POWER.

(iii) for each percent that the magnitude of (q 4 ) exceeds +5 percent, the AT trip set-t b

i point shall be automatically reduced by 0.86 percent of its value at RATED THERMAL POWER.

i 5

5 (1 + '4 ) < AT, { K ' - K5 (1 + T 5 3

) T - K (T-T") - f (AI)}

NOTE 2:

Overpower AT 6

2 4

1+IS S

3 m

  • S

+T5 as defined in Note 1 Where:

4

=

1+I S S

as defined in Note 1

=

T4,IS i

as defined in Note 1 AT

=

g R

K

< 1.087 4

s g

K

= 0.02/*F for increasing average temperature and 0 for decreasing average 5

g temperature

_E 1 S 3

The function generated by the rate-lag controller for T,,9 dynamic

=

g y

73 3

compensation i

H*

4 1

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