W3P85-1290, Forwards marked-up FSAR Page 14.2-136,reflecting Changes to Initial Test Program,Test Subsection 14.2.12.3.31, Control Sys Checkout. Change Deletes 20% Reactor Power Level Test

Forwards marked-up FSAR Page 14.2-136,reflecting Changes to Initial Test Program,Test Subsection 14.2.12.3.31, Control Sys Checkout. Change Deletes 20% Reactor Power Level Test

ML20127J256
Person / Time
Site:	Waterford
Issue date:	05/17/1985
From:	Cook K LOUISIANA POWER & LIGHT CO.
To:	Knighton G Office of Nuclear Reactor Regulation
References
W3P85-1290, NUDOCS 8505210420
Download: ML20127J256 (2)

Text

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MUISIANA

• O W E R & L i G H T / NEW ORLEANS LOUISIANA 442 oe-o~o.r-er

. ao.ox.oo.

70174-8008 9 (504)385-2345 MIODLE SOUTH UTluTIES SYSTEM May 17, 1985 W3P85-1290 A4.05 Director of Nuclear Reactor Regulation Attention:

Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 INITIAL TEST PROGRAM

Reference:

Waterford 3 FSAR, Chapter 14 This submittal-is made in accordance with 10CFR50.59(b) and the license condition in Section 2.C.10 of the subject license. Reported herewith are some changes made to the Waterford 3 Initial Test Program, as described in reference 1, as amended through Amendment No. 36.

The attached marked-up page 14.2-136 (Amendment 18) of the Waterford 3 FSAR reflects the changes made in test subsection 14.2.12.3.3', Control Systems Checkout. The 20% reactor power level test that was scheduled as part of Control Systems Checkout has been deleted from the test schedule. This change to the initial test program does not involve a change in the license technical specifications or an unreviewed safety question. LP&L has conducted and documented the required 10CFR50.59 safety evaluation.

LP&L will provide the FSAR change in accordance with 10CFR50.71(e) requirements. The original plus 39 copies of this report transmittal are prc'nded in accordance with 10CFR50.59(b).

V truly yours, x

N 8505210420 850517

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DR ADOCK 050003a2 V

PDR K.W. Cook Nuclear Support & Licensing Manager KWC:KLB:sms cc:

R.D. Martin, D.M. Crutchfield, J.H. Wilson, NRC Resident Inspectors gh Office, INPO Records Center (J.T. Wheelock), E.L. Blake, W.M. Stevenson

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m WSES-FSAR-UNIT-3 14.2.12.3.31 CONTROL SYSTEMS CPECKGi!T 15 14.2.12.3.31.1 Objective 8

15 To demonstrate that vario'us contr'ol systems operate satisfactorily during steady-state and transient conditions.

8 14.2.12.3.31.2 Prerequisites A.

The Reactor Regulating System (RRS), Feedwater Control System N

(FWCS), Steam Bypass Control System (SBCS), Meg r :: "2 aad "etter 15

(-M99t, Pressurizer Level and Pressure Control System, Hotwell Level Control System, and Boration/ Dilution Systems are in operation or are operable.

B.

The plant is operating at the applicable power level k 50, 80 and l

100 percent).

8 14.2.12.3.31.3 Test Method A.

-Monitor control systems' performance during steady-state operation (g, 50, 80, and 100. percent), and following selected plant trips.-

l B.

Monitor control systems' performance during step and ramp unit lo'ad 15 changes (50 and 100 percent).

D[)

C.

Initiate control system transients on selected control systems, and monitor system response ( X, 50, 80, and 100 percent).

18 l 14.2.12.3.31.4 Acceptance Criteria l0

~

A.

The control systems ma~ntain reactor power, Reactor Coolant System (RCS) temperature 4 re surizer pressure and level, ;ad i;;;..

-m.

k

_aemt.neeson within acceptable ranges during both steady-state and transient operation.

15 B.

The control systems maintain the steam generator levels and pres-I sures, turbine-generator load, and hotwell level within acceptable ranges during both steady-state and transient operation.

hoitf/CHTIGA/ of THIS c gij p'G f g)A S Tiengrm 17T&D To THE ^lA C OH !?? A V /0, / 985. SEG LI0 fL 4.67764 LO3 P85 - /Afs 3 - freorn Xu. Ooose rs G.a). fwiserod.

l DGNO T&S 7WE CHMHGE &L A T6D Y o 7l{/S L Gil0 2 14.2-136 Amendment No. 18, (5/81)

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