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: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:r-g rs
{{#Wiki_filter:r-rs g
                                            ,- oe - . - - e       .m eo-
--h Louisiama ! Newont ANstousea
            --h-Louisiama POWER   & LIGHT! Newont ANstousea    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
,- oe -. - - e
.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:==
==Dear Mr. Knighton:==
==Subject:==
==Subject:==
Waterford 3 SES Docket No. 50-382 License No. NPF-38 INITIAL TEST PROGRAM
Waterford 3 SES Docket No. 50-382 License No. NPF-38 INITIAL TEST PROGRAM
Line 27: Line 28:
==Reference:==
==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.
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.
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).
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 ADOCK PDR P
Very truly yours, 8505150183gj@oh82 PDR ADOCK PDR
PDR                  -
/{
K. . Cook       /{
P K.. Cook Nuclear Support & Licensing Manager KWC:GEW: cms i-1I cc:
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
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%
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s WSES-FSAR-UNIT-3 14.2.12.3.31 CONTROL SYSTEMS CHECKOUT 15 14.2.12.3.31.1 Objective 8
WSES-FSAR-UNIT-3 14.2.12.3.31       CONTROL SYSTEMS CHECKOUT                                             15 14.2.12.3.31.1       Objective                           ,
15 To demonstrate that various control systems operate satisfactorily during steady-state and transient conditions. 1( ;
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.
8 14.2.12.3.31.2       Prerequisites A.     The Reactor Regulating System (RRS), Feedwater Control System (FWCS), Steam Bypass Control System (SBCS), . ,____. __.__._ __.. .
The Reactor Regulating System (RRS), Feedwater Control System (FWCS), Steam Bypass Control System (SBCS),
15
15
                  '"''d , Pressurizer Level and Pressure Control System, Hotwell Level control System, and Boration/ Dilution Systems are in operation or are operable.
'"''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).
B.
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.
The plant is operating at the applicable power level (20, 50, 80 and 100 percent).
Monitor control systems' perfoimiance during step and ramp unit load             15 l          B.
8 14.2.12.3.31.3 Test Method A.
changes (50 and 100 percent).
Monitor control systems' performance during steady-state operation (20, 50, 80, and 100 percent), and following selected plant trips.
[f C.     Initiate control system transients on selected control systems, and i"               monitor system response (20, 50, 80, and 100 percent)-     .                    18
15 l
;          14.2.12.3.31.4       Acceptance Criteria                                             l0
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 -
A.
                -eeeeee64e* within acceptable ranges during both steady-state and transient operation.                                                           15
The control systems aintain reactor power, Reactor Coolant System (RCS) temperature, essurizer pressure and level, :.. i.... x -
: b. The control systems maintain the steam generator levels and pres-sures, turhine generator load, and hotwell level within acceptable i
-eeeeee64e* within acceptable ranges during both steady-state and transient operation.
ranges during both steady-state and transient operation.
15 b.
LP&L W-3 RECORDS UNCONTROLLED COPY
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.
                                        -    p gv c'/JETv -RELATED TESTING, l                                i iTE    ! CE. Ok OFEkATONAL AWM l
i LP&L W-3 RECORDS UNCONTROLLED COPY p gv c'/JETv -RELATED TESTING,
!                                                14.2-136             Amendment No. 18, (5/81) l t}}
! CE. Ok OFEkATONAL AWM l
i iTE l
14.2-136 Amendment No. 18, (5/81) l t}}

Latest revision as of 21:40, 12 December 2024

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 Entergy icon.png
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

r-rs g

--h Louisiama ! Newont ANstousea

,- oe -. - - e

.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

i iTE l

14.2-136 Amendment No. 18, (5/81) l t