ML19220C177

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Evaluation of Baw 10003,Revision 4, Qualification Testing of Protection Sys Instrumentation. Rept Is Adequate Basis for Some Equipment Qualification
ML19220C177
Person / Time
Site: Crane 
Issue date: 11/03/1975
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19220C172 List:
References
NUDOCS 7904300025
Download: ML19220C177 (5)


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.J ENCLOSURE TOPICAL REPCRT EVALUATION Report Number:

EAN-10003 Revision 4 ("on-Proprietary)

Report

Title:

Qualification Testing of Protection Systen Instruacntation Report Date:

April 19 75 Originating Organization:

Babcock and Uilcox, Ccapany Reviewed By:

Branch, Division of Technical ReviewSection A - Electrical, Instrumentation and Summary of Tociaal Renort The topical repert pres. cats the results of the seismic and enviren;cntal qualification testing of the protection system instrumentation useu Babcock and Wilcox nuclear steam systems including:

in detectors, signal conditioning instrun-atation, pcwcr supplies, test signal generaters, and relay logic.

Surmarv of P.cgulatorv Evaluation As a result of our reviev, we have concludsd that this topical report provides satisfactory ansucrs to the questions which ucre transmitted as basis for the qualificatica cf sc:a equipmenta result of our revicu of R in older plants.

_Summarv.of Reculatorv Pos# tien 1.

The subject report in its present form provides an acceptable basis for testing instrunents and control devices to demonstrate the capability of this equipment to function with precision and reliability over the full range of transient and steady-state conditions of both the energy supply and the environment during normal, abnormal, and accident circunctances throughout which the instruncatation cust perform.

2.

The testing which is presented in the subject report dces not satisfy all of the requirc ents of IEEE Std 323-1974, which was published February 28, 1974 docketed for a construction permit after that date.and can not be used as 3.

RAW-10003 Revision 4 =ay be used as a basis for licensing plants in which constructica pcrait second round questions were issued prior to April 30, 1974.

4.

The subject report is not applicable to solid state logic systems such as RPS-II.

5.

The subject report la caly applicable to the folleving portions of the reactor prote'etion systen:

Cronu I - Anolifier Modules 88 091 Prcamplifier Count rate amplifier g{

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Rate-of-change acclifier Euffer amplifier (A)

Linear amplifier Logarithmic a:plifier Square root extractor Lincar bridge Signal converter Sun /differenca amplifier Function generatcr Group II - Pouer Sunniv Modules System power supply ("

Detector power supply Auxiliary pouer supply Group III - Test Modules Source range test Intermediate range test Power range te.st Tenperature test Flow test Pressure test (a)

Contact conitor test Group IV - Lonic Modules

. Bistable "

. Contact tonitor Group V - Relav Modules Auxiliary relay ("}

Reactor trip assembly Contact buffer (b)

Logic buffer (b)

Logic test (b)

Unit control (b)

Trip lcgic (b)

( ) Modules that are interchangeable between the NI/RPS and the SFAS.

(b) Modules associated only with the SFAS (modules associated cnly with the NI/nPS have no indicator).

Detectors Pressure,(Foxboro)

Prcscure (:lotorola)

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Differential Pressure (Bliley)

Temperature (Resecount Models 177 GX, JD, and H)

Pressure Switch (Mercoid)

Neutron Detectors Therefore, the scismic and environ =catal qualifications of the remainder of the Class IE equipacnt in an application.nust be reviewed separately.

6.

The individual applications must de=onstrate that the equip =cnt will comply to the following interf ace criteria in its as installed condition:

The still air temperature of the equipment cust be =aintained within a a.

range of 40 to 110*F at relative humiditics of 50%,

b.

The interconnecting vising and connectors must be qualified to meet the environ =catal and scisaic plant design criteria.

The electrical power sources for the instrumcatation shall maintain c.

input to the cabinets of 107 to 127 V ac at 58 to 62 H:.

d.

The applicant's Chapter 15 analysis shall be based on assumcd crrors for the following equipment which are not less than those listed herci..-

(1) Reactor Ccolant Pressure Foxboro Equip:ent

+ 1. 85%

Motorola Equipacnt

+ 3.69%

(2) Reactor Coolant Flcu

+ 3.0%

(3) Reactor Coclant Te=perature

+ 1. 0%

(4) Reactor Ccolant Pump Status

+ 0.88%

Monitor (5) Reactor Building Pressure

+1.0%

-50%

(6) Neutron Monitoring Total Flu::

+ 4.0%

Flux Imbalance

[5.0%

88 093 If Motorola Pressure sensors are used, the technical specificaticas c.

shall require calibration not less frequently than once eyery {/ 3 pur conths.

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f.

The analysis in Chapter 15 of the Saf ety Analysis Report shall be based on assumed response times uhich are equal to or greater than nn

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-4 the following times required for a response to 99'; of the differential change fres a step input:

(1)

Pressure Detectors 250 msec.

(2) Differential Pressure 250 msec.

Detectors (Flow)

(3) Temperature Detectors Models 5 sec*

177 CX and JD Hodel 177 H 3 sec*

  • time to change 63.2% of applied step change in input (4) Preamplifier 100 ns rise time (5) Count rate amplifier 400 s 0 0.1 Hz 1 s 0 106 n:

(6) Ratc'of-change amplifier

< 10s (7) Euffer amplifier 50 ms, 1 s (8) Linear amplifier

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50 ms

-1l (9) Logarithmic amplifier 10 s 0 10 A

3 0.1 s G 10 A

(10)

Square root extractor Incr 250 ms Deer 500 ms (11) Lincar bridge 10 ms (12)

Signal converter 300 ms (tcep output)

, (13)

Signal converter 300 ms (press, output)

(14)

Sum / difference amplifier E

10 ms out Scaled E, 10 ms g q j, N,O Ui t (15)

Function generator Slope 15 ms e

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.) 100 es (16) 31 stable 30 ms (17) Reactor Trip (interlock or test trips)

(18) Contact Buffer Modulca 40 ns cnergize de-energize 100 ms 10 ms (19) Logic Euffer Module (20) Unit Control Module Trip 50 ms The applicant shall provide reactor coolant pump status monitors g.

and detectors t:hich shall have a combined accuracy of 0.SS% and a response time of 6 cs or less.

h.

The applicant shell provide a description of and procedures for testing to assure that,the equip =cnt is more accurate than and responds in a shorter t -

  • b n the limits presented in req'uirements (d),

d (f), and (g) above.

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