W3P85-3209, Forwards Changes to Chapter 14 to Fsar,Deleting Control Sys steady-state Operation at 100% Power Level & Deleting Movable in-core Detector Responsiveness Testing from Power Ascension Test Program

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Forwards Changes to Chapter 14 to Fsar,Deleting Control Sys steady-state Operation at 100% Power Level & Deleting Movable in-core Detector Responsiveness Testing from Power Ascension Test Program
ML20205E228
Person / Time
Site: Waterford Entergy icon.png
Issue date: 10/15/1985
From: Cook K
LOUISIANA POWER & LIGHT CO.
To: Knighton G
Office of Nuclear Reactor Regulation
References
W3P85-3209, NUDOCS 8510170233
Download: ML20205E228 (8)
v • d • e


Text

l.OUISIANA 242 ouAnoNm sinur POWE R & L1GHT P O box tsOOO. NEW OnLE ANS LOutSIANA 70174 1504r 366 2345 N uS N E sY $

October 15, 1985 W3P85-3209 A4.05 QA

, Director of Nuclear Reactor Regulation Attention:

Mr. G. W. Knighton 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 10 CFR 50.59(b) and the license condition in Section 2.C.10 of the subject license. Reported herewith are two changes made to the Waterford 3 Initial Test Program, as described in the referenced document, as amended through Amendment No. 36 The changes to the initial test program are:

1.

Deleted the Control &ystems steady-state operation checkout at 100%

power level. The attached marked-up page 14.2-136 (Amendment 18) of the Waterford 3 FSAR reflects the change in test subsection 14.2.12.3.31, Control Systems Checkout. The marked-up FSAR page also shows the notifications of previously reported changes to this test.

Individual control system monitoring at 50%, 80% and 100%; plus the integrated control system monitoring at 50% and 80%, and integrated control system ramp unit load changes at 100% provide sufficient checkout of the control systems.

This change does not involve a change in the license technical specifications or an unreviewed safety question. The control systems described in this test are not safety related and no credit for their operation is taken in any of the Waterford 3 FSAR Chapter 15 analyses.

2.

Deleted the Movable Incore Detector responsiveness testing from the power ascension test program. The Movable Incore Detector System (FSAR test subsection 14.2.12.2.58) is not required to support any safety analyses. The attached marked-up pages 14.2-89 (Amendment 34),

14.2-161, 14.2-162, 14.2-163 and 14.2-164 (Table 14.2-5, Amendment 35) reflect the deletion of this testing.

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i Mr. G. W. Knighton i

W3P85-3209

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Page 2 1

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l This deletion does not involve a change in the license technical j

specifications or an unreviewed safety question.

1 LP&L has conducted and documented the required 10 CFR 50.59 safety j

evaluations for these changes. LP&L will provide the FSAR changes in accordance with 10 CFR 50.71(e) requirements. The original plus 39 copies of this report transmittal are provided in accordance with 10 CFR 50.59(b).

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Very truly yours, 1.

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l K.W. Cook i

Nuclear Support & Licensing Manager

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RsD. Martin, J.H. Wilson, NRC Resident Inspectors Office, B.W. Churchill, W.M. Stevenson I

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> coa-t u WSES-FSAR-UNIT-3 I

14.2.12.3.31 CONTROL SYSTEMS CHECK 0UT 15

.2.12.3.31.1 Objective 14 8

To demonstrat'e that various control systems operate satisfsetorily during 15 steady-state and transient conditions.

14.2.12.3.31.2 Prerequisites r

A.

The Reactor Regulating System (RRS), Feedwater. Control System' (FNCS)', Steam Bypass Control System (SBCS), M:;; h::: 5 :: d S::::

h

'"" O, Pressurizer Level and Pressure Control System, Rotwell Level O

I Control System, and Boration/ Dilution Systema are in operation or are operable.

B.

The plant is operating at the applicable power level (%, 50, 80 and @

100 percent).

8 14.2.12.3.31.3 Test Method A.

Monitor control systems' performance during steady-state operation

(% 50, 80, end-% percent), and following selected plant trips.

@ h B.

Monitor control systems' performance during M(Y# ramp unit load g 15 changes MMIWpf 100 percent).

!Cb-Initiate control system transients on selected control systems, and

/;

C.

monitor system response (K. 50, 80, and 100 percent).

h 18 14.2.12.3.31.4 Acceptance criteria l8 1

A.

The con. trol system intain reactor power, Reactor Coolant System (RCS) temperature pressuriser pressure and level h

8--

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.

NOTES:

h Change notification made by LP&L letter W3P85-1263 dated 5/10/85.

h Change notification made by LP&L letter W3P85-1290 dated 5/17/85.

~

h Denotes the change by this transmittal (W3P85-1432).

h Denotes the change by this transcrittal (W3P85-3209).

LP&L W-3 RECORDS UNCONTROLLED COPY CO NOT USE !N ANY CAFE 1Y -RELATED TESTING.

MAINTEN ANCd. OR OFEilATiCNAL ACTIVITY 14.2-136 Amendment No. 18. (5/81) 1 l

l

WS ES-FSA R-UNIT-3 14.2.12.2.58 MOVABLE INCORE DETECTOR SYSTEM 29 14.2.12.2.58.1 Objective 8

To verify the proper performance of the Movable Incore Detector System.

15 14.2.12.2.58.2 Prerequisites 8

A.

Construction activities on the systems to be tested are complete.

l18 B.

Pemanently installed instrumentation is operable and calibrated.

C.

Plant systems required to support testing are operable, or temporary systems are installed and operable.

15 D.

Test instrumentation is avail 1ble and calibrated.

14.2.12.2.58.3 Test Method 8

A.

Operate one set of drive and transfer machines at a time and record all pertinent outputs, including encoder signals.

B.

Using external instrumentation, simulate the plant computer command signals to drive the detectors and to change inlet-to-outlet instru-15 ment loop alignments. Monitor all feedback signals as required for verification of simulated commands.

C.

Operate the system from the main control room board and verify proper operation by monitoring the feedback signals.

D.

Operate the system from the local position with the portable control 15

, set and verify proper operation by monitoring the feedback signals.

14.2.12.2.58.4 Acceptance Criteria The Movable Incore Detector System performs as described in Subsection 15 7.7.1.7.

..a r LP&L W-3 RECORDS UNCONTROLLED COPY CO NOT USE IN e NY CAFE 1 Y -RELATED TEST!NG.

MAINTEN ANCJ.. OR gee *lATiCNAL ACTIVITY

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cechan 1 opera lity o he syste will be te ted prior fuel ad.

4 Ho ver, th detecto espon iv ess a d mpariso sting w*

1 be d 4

at r fuel lo

/

14.2-89 Amendment No. 34, (1/84)

WSES-FSAR-UNIT-3 i

TABLE 14.2-5 POWER ASCENSION TESTING SEQUENCE 18 Power Tests 20% Power Plateau

1) Biological Shield Effectiveness Survey (14.2.12.3.15)*
2) Process Variable Intescomparison (14.2.12.3.30)*

31

3) Chemistry and Radiochemistry (14.2.12.3.19)*
4) Baseline Vibration and Loose Parts Monitoring (14.2.12.3.40)*
5) Deleted 35
6) Nuclear and Thermal Pover Calibration (14.2.12.3.27)
7) Core Performance Record (14.2.1'2.3.27)
8) %vab(IncheDeKctfCh (1%.1

)

9) CPC/COLSS Verification (14.2.12.3.28)
10) Shape Annealing Matrix (14.2.12.3.28) l35
11) Load Changes (Control Systems Checkout)

(14.2.12.3.31) 12)' Remote Reactor Trip with Subsequent Remote Plant 37 Cooldown (14.2.12.3.33)

.wrr LP&L W-3 RECORDS UNCONTROLLED COPY CO NOT USE !N d NY CAFE 1 Y -RELATED TEST!NG.

MAINTEN ANCd. OR OFEHATiCNAL ACTIVITY 14.2-161 Amendment No. 35, (5/84)

WS ES-FSAR-UNIT-3 TABLE 14.2-5 (Cont'd) 18 Power Tests 50% Power Plateau

1) Process Variable Intercomparison (14.2.12.3.30)*
2) Chemistry and Radiochemistry (14.2.12.3.19)*
3) Reactor Internals Vibration Monitoring (14.2.12.3.40)*
4) Biological Shield Ef fectiveness Survey (14.2.12.3.18)*
5) Ventilation capability (14.2.12.3.42)*
6) Nuclear and Thermal Power Calibration (14.2.12.3.27)
7) Core Performance Record (14.2.12.3.27)

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9) CPC/COLSS Verification (14.2.12.3.27) 35 101 Temperature Decalibration Verification (14.2.12.3.28) 11)* Shape Annealing Matrix (14.2.12.3.28)
12) Radial Peaking Factor Verification (14.2.12.3.28)
13) Variable Tavg (14.2.12.3.26) 29
14) Load Changes (Control Systems Checkout)

(14.2.12.3.31)

15) RPCS 50% Loss of Load (14.2.12.3.39) l34 Pre 80% Power Plateau 1)

RPCS 70% toss of one Operating Feedwater Pump (14.2.12.3.42) 31 2)

Atmospheric Steam Dump and Turbine Bypass Valve Capacity Checks (14.2.12.3.29)

. c,2 r r 35 LP&L W-3 RECORDS UNCONTROLLEO COPY CO NOT USE IN e NY CAFElY -RELATED TESTING.

MAINTENANCd. OE OFE~tATiCNAL ACTIVITY 14.2-162 Amendment No. 35, (5/84)

WS ES-FS AR-UNIT-3 TABLE 14.2-5 (Cont'd) 18 Power Tests 80% Power Plateau

1) Process Variable Intercomparison (14.2.12.3.30)*
2) Chemistry and Radiochemistry (14.2.12.3.19)*
3) Reactor Internals Vibration Monitoring (14.2.12.3.40)*

29

4) Nuclear and Thermal Power Calibration (14.2.12.3.27)
5) Core Performance Record (14.2.12.3.27)

Dhec%rC

(

n es ry) 6)

o

7) CPC/COLSS Verification (14.2.12.3.27) l35
8) Load Changes (Control Systems Checkout)

(14.2.12.3.31) 29

9) 80% Total Loss of Plow / Natural Circulation Test 34 (14.2.12.3.25)
10) RPCS 80% Loss of Load (14.2.12.3.38) l31 Post-80% Power Plateau 1). Loss of Offsite Power Trip (14.2.12.3.35 and.41) 18
2) Load Changes (Control Systems Checkout)

(14.2.12.3.31)

3) Nuclear and Thermal Power Calibration 29 (14.2.12.3.27)

LP&L W-3 RECORDS U \\lCONTROL=EO COPY CO NOT USE IN e NY CAFE 1 Y -RELATED TEST!NG.

MAINTENANCd. OR OPEitATiONAL ACTIVITY 14.2-163 Amendment No. 35, (5/84)

WSES-FS AR-UNIT-3 I

TABLE 14.2-5 (Cont'd) 18 Power Tests 100% Power P1:steau

1) Process Variable Intercomparison (14.2.12.3.30)*

l29

2) Chemistry and Radiochemistry (14.2.12.3.16)*

l 34

3) Reactor Internals Vibration Monitoring (14.2.12.3.40)*

29

4) Biological Shield Ef fectiveness Survey (14.2.12,3.15)*

l 34

5) Ventilation Capability (14.2.12.3.32)*

l31

6) Nuclear and Thermal Power Calibration 29 (14.2.12.3.27)*

l 34

7) Core Performance Record (14.2.12.3.27) c

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9) CPC/COLSS Verification (14.2.12.3.27) l35
10) Variable Tavg (14.2.12.3.26) 29
11) Load Changes (Control Systems Checkout)

(14.2.12.3.31 and.39)

12) 100% Turbine Trip - Load Rejection (14.2.12.3.38)
13) 100% Generator Trip - Load Rejection 34 (14.2.12.3.38)

The table is representative of the actual testing sequence to be performed at Waterford SES 3.

However, based on future startup experience, the testing sequence may be modified to improve and/or optimize testing.

LP&L W-3 RECORDS UNCONTROLLED COPY CO NC E USE !N e NY SAFE 1 Y -RELATED TEST!NG.

13 mal.NTENANCd. OR gee;IATiCNAL ACTIVITY

  • May be conducted at any time during tne test ptaceau. All other tests are expected to be accomplished in the order given.

14.2-164 Amendment No. 35, (5/84)

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