ML20215L320

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Forwards Revised FSAR Section 14.2.8.2.57 Re at-power Intercomparison of Reactor Protection Sys Inputs & Plant Computer Outputs Test to Define How Inputs to Sys Read for Comparison to Plant Computer
ML20215L320
Person / Time
Site: Vogtle 
Issue date: 06/19/1987
From: Gucwa L
GEORGIA POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
SL-2695, NUDOCS 8706260011
Download: ML20215L320 (3)


Text

.-

' +V

. Georgia FowQt Cornpany 333 Piedrnont Avenue' - ~

~ Atlanta. Georgia 30308 Telephone 404 526 6S26

' Malling Mdress:

Post office Box 1545 Atlanta, Georgia 30302 h

' Georgia Power

'L.T.Gucwa the southem electre system Manager Nuclear. Safety

. and Licensing r

SL-2695 0356m X7GJ17-V750 June 19, 1987 U. S. Nuclear. Regulatory Commission ATTN: Document. Control Desk.

Hashington, D.C.

20555-PLANT V0GTLE - UNIT 1

'NRC DOCKET 50-424 OPERATING LICENSE NPF-68 i

CHANGES IN INITIAL STARTUP TEST PROGRAM j

Gentlemen:

l The following' information is provided in accordance. with Operating l

License Condition 2.C.(3) whereby Georgia Power Company:is tol report any.

j changes-to the Initial Test Program described in Section 14 of -the FSAR made in accordance with'the provisions of 10 CFR 50.59.

The At-Power Intercomparison of Reactor Protection System Inputs and Plant Computer Outputs Test, described in FSAR Section 14.2.8.2.57, has been revised to clarify the test method.

This change was made to define' how the inputs to the reactor protection system-are read for comparison to.the plant computer.

Enclosed is an abstract of the revised test.

The revision to the test abstract will be incorporated in a future FSAR amendment.

Please contact this office if you have any questions.

l i

Sincerely, l

[ A^~"

L. T. Gucwa EMB/lm

Enclosure:

1.

Test Abstract Revision c:

(see next page) x

, _ 4 O W 424.

A PDR b.

.w i

)

Georgia Power A 4

U. S. Nuclear Regulatory Commission-June 19, 1987 1

-).

Page Two

']

. i, c: Georaia Power Comoan'y j

Mr. R. E. Conway 4

Mr.'J. P. O'Reilly i

Mr, G. Bockhold, Jr.

1 Mr. J. F. D'Amico Mr. C.-H. Hayes GO-NORMS.

Southern Comoany Services l

Mr. R. A. Thomas Mr. 'J. A. - Bailey i

Shaw. Pittman.~Potts & Trowbridae l

Mr. B. H. Churchill, Attorney-at-Law I

Troutman. Sanders. Lockerman & Ashmore Mr. A. H. Domby, Attorney-at-Law i

U. S. Nuclear Reaulatory Commission f

Dr. J.;N. Grace, Regional Administrator Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)-

'Mr. J. F. Rogge,-Senior Resident Inspector-Operations, Vogtle Georaians Against Nuclear ~Enerav 4

Mr. D. Feig 1

Ms. C. Stangler~

c q

l 1

0356m 1

- roons i

m

  • :i -

g

+Nl LGeorgiaPower A '

ENCLOSU'RE PLANT V0GTLE ' UNIT 1 1

1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 CHANGES IN INITIAL STARTUP TEST PROGRAM'

'14.2.8.2.57 At-Power 'Intercomparison of Reactor Protection System In' puts and'P1 ant Computer Outputs Test JA.

-Objective 4

ToEdemonstrate that. the inputs to the reactor protection system l

and 'the-plant computer are in satisfactory agreement with one

{

another.

f)

B.L Prerequisites l '.

.The' plant is at steady state conditions at the applicable power level (30, 50, 75, and 100 percent).

2.

Permanently installed instrumentation is calibrated and operable.

C.

' Test Method-1.-

Take simultaneous readings of. the inputs to the reactor protection system as read from the main control board or

.l

other accessible locations and the output of 'the plant l

computer.

.i 2.

Evaluate the readings taken.

D.

Acceptance Criterion

-l The inputs of the reactor protection system and outputs of the l

plant computer agree within the combined accuracy of the individual instruments.

i 0356m E-1 06/19/87

' SL-2695 l

700770

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