ML20236H213

Forwards Fourth Status Rept,Identifying Changes to Initial Test Program Described in Fsar,Chapter 14,per 10CFR50.59(b)

ML20236H213
Person / Time
Site:	Beaver Valley
Issue date:	10/27/1987
From:	Carey J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
2NRC-7-208, TAC-63534, NUDOCS 8711030519
Download: ML20236H213 (8)

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DucluesneLight I Beaver Valley No. 2 Unit Project Organization (412) 643-5200 ..

- Telecopy (412) 643-5200 Ext.160 S.E.G. Building P.O. Box 328 ~

Shippingport, PA .15077 0ctober 27,'1987 2NRC-7-208; 3 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 i

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SUBJECT:

Beaver Valley Power Station Unit No. 2 q l

Docket No.-50-412 BVPS-2 FSAR Chapter 14, Test Change. Status Report ]

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Gentlemen: f Forwarded to NRC is the fourth status re.nor t . identifying changes to the j j

Initial Test Program as described in Chapter 14,;of the FSAR. These changes are made in accordance with the provisions: of -10CPR50.59 and reported to NRC in- l accordance'vith 50.59(b) within one month of. Einitiating changes per BVPS-2 i Facility Operating License Condition C.(3).  !

1 DUQUESNE LIGHT COMPANY. .j i

(/ _ J.Gd. Carey(/ '  ;

Senior Vice President l VRB/ij r M11/WRB/NRC/ STATUS Att ment AR/ JAR cc: Mr. P. Tam, Project Manager (w/a)

Mr. J. Beall, NRC Sr-. Resident Inspector .(v/a) .

1 Mr. P. Ven, NRC Reactor-Engineer, Region I (w/a)'

INPO Records Center (w/a)  ;

M B711030519 871027 PDR ADOCK 05000412 p enn T

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BVPS-2 FSAR Chapter 14 Test Change Status Report

References:

(a) DLC letter 2NRC-7-172, dated July 6, 1987, Mr. J. J. Carey to U. S. Nuclear Regulatory Commission j (b) DLC letter 2NRC-7-205, dated September 30, 1987, Mr. J. J.

Carey to U. S. Nuclear Regulatory Commission FSAR Section Title i

1) 14.2.12.48.01 Main Plant Carbon Dioxide Fire Protection (SOV 2.33A.01) System Test (SOV)

Reference (a) provided a commitment to complete acceptance testing of C0 suppressionsystemproposedmodificationsincludingpressurerelief-pathsbh l September 30, 1987. Reference (b) identified this testing was deferred l until December 31, 1987 due to the inability to complete modification.on '

time. Compensatory measures are provided as identified in' reference (b).

There are no Technical Specific ation requirements associated with this system. l l

2) 14.2.12.6.6 Load Sving Test (IST) l (IST-2.04.04) ]

This test abstract is being revised per Attachment A to delete the ~ 10%  !

power load swing at 75% power. Credit for this load sving is obtained by the scheduled performance of IST-2.04.05 "Large Load Reduction Test For Turbine Runback" at 75% power with a 50% load reduction. 'This change does i not affect any Technical Specification requirements.

3) 14.2.12.4.8 Incore/Excore Detector Calibration for Axial l Offset Measurement (IST)  !

.l Test IST-2.02.07 was scheduled to be . performed at 75% power to meet the intent of this abstract. Test procedure BVT 2.1-2.2.3 " Nuclear Power Range Calibration" was performed at 50% power which also meets the intent of this abstract and is used to satisfy part of Technical Specification 4.3.1.1.1.

Westinghouse concurred with the use of BVT 2.1-2.2.3 at 50% power in place of IST-2.02.07 at 75% power. Therefore, this test abstract is being revised-

. per Attachment B to reflect this change.

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BVPS-2 FSAR' Chapter 14 Test Change' Status Report (cont'd) '

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'l FSAR Section Title j 1

4) 14.2.12.73.02 .Non-0ACategoryI-Heat [ Tracing.SystemTest (S0V),

Test'S0V-2.45D.01 vas scheduled.to bel l completed'during the Power Ascentioni 1

, Program.. The- systems involved :are. operable 'however~, only: 75%:of thei  !

circuits are. :successfully tested. Final = testing ~'is; scheduledito'be t

completed prior to December 15, 1987. There'are no. Technical Specification a requirements associated.withi hese t systems.

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5) :14.2.12.6.7. :Large. Load. Reduction TestLfor. Turbine (IST-2.04.05) ' Runback (IST) i J

This test abstract is being revised perf Attachment C'to delete.the 50% load' reduction at 100% power. Regulatory ;Guidefl.68, " Initial. Test Programs.fori '

Water-Cooled Nuclear. Power Plants" has':been: reviewed and does'not' require this test. This change- does : notc affect -any-: Technical Specification j

requirements. l

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l ATTACHMENT A 1 l

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4. The turbine driven ausiliary feedwater pump will be verified to cold, quick start automatically and operate for at least 1/2_ hour  !

er until the plant stabilizes with loss of all offsite power..

Acceptance criteria.

.1. The ability of 'the. plant to sustain a turbine trip coincident-with loss-of-offsite power at load has been demonstrated.

4 l 2. The turbine-driven auxiliary feedwater pump automatically, quick starts, and remains within design limits .with . respect ' :to bearing / bearing- oil temperatures and. vibration.- Pump ' rcom - .

ambient conditions ( tempe rature ,' ' humidity). de . not exceed 'I environmental qualification limits'for safety-related equipment in the room.

14.I'.12.4. ..8 Load Swing Test (IST)

Test objectives To verify the proper -transient response of .the plant and the l autoestic control systems during step and' reap load changes at l various plant' power levels and todemonstratetheabilityofthej j charging system to respond to step load changes.

Prerequisites

1. Required plant control systems are in the automatic control mode.

2. The plant. is in operational mode 1 with reactor power-level l established as required. ]

e Test tiethods ..

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1. Design step .and ramp load changes will be applied at each power level (approximately 30, % and.100 percent) during power ascension tes' ting. i

2. The primary and secondary plant parameters.will be monitored as required to verify the proper response- of the . plant and its automatic control systems. -i Acceptance criteria Plant parameters remain within design specifications throughout the application of each load change, and the automatic . control -systems re-establish stable operation at each new power level.

Amendment 12 14.2-46 ,

June 1986

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ATTACHMENT B BVPS-2 FSAR.

Acceptance Criteria The extrapolated 100 percent value of AT and T av for each channel is withinacceptablelimitsoftheaverageofallchannels.

14.2.12.4.7 Thermal Power Calorimetric Measurements (IST) f Test Objectives k

To determine the reactor core thermal power output from secondary l side calorimetric measurements at approximately 30 , 50 , 75 , 90 , i and 100-percent power levels.

Prerequisites The plant is in operational mode 1 with. reactor power level established as required.

Test Methods

1. The plant will be verified to be at steady state conditions.

Secondary plant calorimetric data, such as steam pressure, feedwater flow, and feedwater temperature will be measured.

Steam generator blowdown operating parameters will be measured if the system is not isolated.

2. Reactor core thermal power output will be calculated from the calorimetric data accounting for heat losses and heat gains from the reactor coolant pumps.

Acceptance Criteria Not applicable 14.2.12.4.8 Incore/Excore 4ector Calibration for Axial Offset Measuremtn (IST) q l

Test Objectives

1. To demonstrate that the response of the excore power range j detectors is linear with respect to incore axial. power-distribution. J

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2. I To calibrate the excore power range detector input and excore l power range detector signals.

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Prerequisites

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Test data is available from a minimum of three movable deltator flux map,g o @ d over a range of incore axial offsets,[oi at least #

15 percent.

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ATTACHMENT B' l

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BVPS-2 FSAR ]

1 Test Methods j j

1. Calculations, utilizing prior' testL data, will be performed to l L R demonstrate that the response of the excore power range detectors is linear with respect to incore axial power distribution. , j l

2. The excore power' range detector input will be calibrated to the j AT reactor trip set point calculator, j

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3. The excere power range detector signals to the ; axial flux- j l difference. Aq. meters, and flux recorders will be calibrated. I i

Acceptance Criteria

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1. The response .of the excore power range detectors is linear with A respect to incore axial power. distribution. ,

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2. The excore power range detector input and-excore power range  ;)

detector signals are properly calibrated.,

14.2.12.5 Reactor,Incore Instrumentation System ' I 14.2.12.5.1 Incore Moveable Detector System Checkout (IST)

Test Objectives

1. To demonstrate system operation for incore flux mapping.

2. To provide a check of the associated leak detection and gas purge subsystems.

Prerequisites

1. The applicable general prerequisites, as listed in Section 34.2.12.1.1, are met.

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2. Fuel loading is complete.

Test Methods

1. Prior to initial criticality, each detector drive assembly will be tested in.the insert and withdrawal mode for each detector path to demonstrate proper operability of the system. The top and bottom core set points will be established for each detector path within the core.

2. The leak detection system will be checked for proper operation by

1. manually simulating a leak with the float. pressure. switch and verifying that the drain valve opens and the alarm actuates.

Amendment 5 14.2-40 February 1984 L . - _ _ - _ _ -

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, s 1 14.2.12.6.7- .Large 1 Load. Reduction. Test For Turbine' Runback:(IST),.

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' Test Objectives.

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To iverify the'~ proper transient'L. response of .the planth and the- ,

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-; automatic < control systems: during the ' load reduction as a. result' of. a:l j

turbine runback and to demonstrate.the.abilityfof the charging system to respond to large step. load reductions. '

L Prerequisite's' ,

9 :q 1 The planti is.'in' operational' mode.'1 at a steadyLst' ate power. level of' '

approximately75(and10@percentpowergsrequire ,  ;

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Amendment 11 '14.2-46a. . January 1986.

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,q Test MethoCs. .

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1. Atjpower level f approk ht.h ly 75 M percen.t, a 50-percent ,

power decrease will be initiated by rapidly closing the turbine M- 1 governor valve. un'cil the- primary plant reaches the . desired power .

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( level. The rate of power ' change) shouldS.be ' approximately < 200 percent per minute.

2. The transieni ' p15nt parameters;will be . monitored 'as required to % l verify the proper response ofithe plant:and its automatic control. r

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3. Whin the -lower;powdrhavel is reached, th'e reactor control rods '

will be manually' adjusted for plant. operation at the new load.- 4. .

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Acceptahee criteria k>

, ;ic The reactor and-tu'rbine'do not trip during the test.

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2. The- automatic control systems. return- the plant ;to'a stable j operating condition, 'and' the plant ' operating parameters- are'  ;

. within design specifications.

l 14.2.12.6.8 Verification Of Plant Performance Following Plant' Load Rejection / Trip From Power.(IST) , , ,

Test Objectives t To verify the proper transient ' response of the automatic control i systems following a net load rejection from 50 and.'100 percent . power -I and a plant trip from 100 percent power. y a s i Prerequisites A ,

1. The plant is in operational mode 1 near 50 percent ore 100 percent rated thermal power as appropriate. :a 'w' , .i sp 1

2. Plant trips at lower power levels have been performed during ).y l power ascension testing. '

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Test Methods .

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1. - At 50 and' then 100 percent power, a net ~1oad rejection will:be  ;

initiated by tripping the mainLtransformer 345 kV L p,owert, circuit /

breakers. At 100 percent power, a' plant trip will"be' initiated

2. bytrippingthemainturbinci.,-(('nitoredasrequiredtove The plant parameters will be mo

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. proper operation of the plant and automatic control' systems.

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