W3P85-1263, Forwards marked-up Page 14.2-136 of Amend 18 to FSAR, Reflecting Changes in Test Subsection 14.2.12.3.31 Re Control Sys Checkout.Megawatt Demand Setter Deleted as Test Prerequisite Because Plant Design Does Not Have Setter
| ML20117J693 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/10/1985 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| W3P85-1263, NUDOCS 8505150183 | |
| Download: ML20117J693 (2) | |
Text
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.m eo-POWER & LIGHT 7ot74-ooos e (sodisee as4s MIDDLE SDUTH UTluTIES SYSTEM May 10, 1985 W3P85-1263 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
Dear Mr. Knighton:
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 14.2.12.3.31, Control Systems Checkout. The Megawatt Demand Setter (MDS) was deleted as a test prerequisite because our current plant design does not have an MDS.
Boron concentration is deleted under acceptance criteria since it is maintained manually not by a control system. These changes to the initial test program do 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(c) requirements. The original plus 39 copies of this report transmittal are provided in accordance with 10CFR50.59(b).
Very truly yours, 8505150183gj@oh82 PDR ADOCK PDR
/{
P K.. Cook Nuclear Support & Licensing Manager KWC:GEW: cms i-1I cc:
R.D. Martin, D.M. Crutchfield, J.H. Wilson, NRC Resident Inspectors Office, INPO Records Center (J.T. Wheelock), E.L. Blake, W.M. Stevenson
,C%
s WSES-FSAR-UNIT-3 14.2.12.3.31 CONTROL SYSTEMS CHECKOUT 15 14.2.12.3.31.1 Objective 8
15 To demonstrate that various control systems operate satisfactorily during steady-state and transient conditions. 1( ;
8 14.2.12.3.31.2 Prerequisites A.
The Reactor Regulating System (RRS), Feedwater Control System (FWCS), Steam Bypass Control System (SBCS),
15
'"d, 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 (20, 50, 80 and 100 percent).
8 14.2.12.3.31.3 Test Method A.
Monitor control systems' performance during steady-state operation (20, 50, 80, and 100 percent), and following selected plant trips.
15 l
B.
Monitor control systems' perfoimiance during step and ramp unit load changes (50 and 100 percent).
[f C.
Initiate control system transients on selected control systems, and i"
monitor system response (20, 50, 80, and 100 percent)-
18 14.2.12.3.31.4 Acceptance Criteria l0
[
A.
The control systems aintain reactor power, Reactor Coolant System (RCS) temperature, essurizer pressure and level, :.. i.... x -
-eeeeee64e* within acceptable ranges during both steady-state and transient operation.
15 b.
The control systems maintain the steam generator levels and pres-sures, turhine generator load, and hotwell level within acceptable ranges during both steady-state and transient operation.
i LP&L W-3 RECORDS UNCONTROLLED COPY p gv c'/JETv -RELATED TESTING,
! CE. Ok OFEkATONAL AWM l
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14.2-136 Amendment No. 18, (5/81) l t