ML19308E228
| ML19308E228 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/30/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19308E225 | List: |
| References | |
| NUDOCS 8003240770 | |
| Download: ML19308E228 (5) | |
Text
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TOPICAL REPORT EVALUATION Report Number:
BAW-10003 Revision 4 (Non-Proprietary)
Report
Title:
Qualification Testing of Protection System Instrumentation Report Date: April 1975 Originating Organization:
Babcock and Wilcox, Company Revi,cwed By:
Section A - Electrical, Instrumentation a.nd Control Systems Branch, Division of Technical Reviev Summary of Topical Report The topical report presents the results of the scismic and environ =cntal r
qualification testing of the protection system instrumentation used in Babcock and Wilcox nuc1 car secam systems including:
detectors, signal.
conddtioning instrumentation, power supplies, test signal generators, and relay logic.
Summary of Regulatory Evaluation As a result of our revicu,'we have concluded that this ' topical report provides satisfactory answers to the questions which were transmitted as a result of our revicu of Revisions 2 and 3 and is therefore an acceptabic basis for the qualification of some equipment in older plants.
1 Summary.of Regulatory Position 1.
The subject report in its present form provides an acceptabic basis for testing instruments 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 environ cnt during normal, abnormal, and accident circumstances throughout which the instrumentation must perform.
- - ~
2.- Th~c testing which is presented in the subject report does not satisfy all of the requirements of IEEE Std 323-1974, which was published February 28, 1974 and can not be used as a basis for licensing plants do'cketed for a construction permit af ter that date.
3.
BAW-10003 Revision 4 cay be used as a basis for licensing p'lants in which construction permit second round questions werd issued prior to April 30, 1974.
4.
The subject-report -is not applicable to solid state logic systems such
. as R1'S-Il.
5.* The subject report is only applicabic to the following portions of the reactor prote'etion system:
Group 1 - Ac'plifier Modules O27b Preamplifier Count' rate acplifier 8003 L
-2 Rate-of-change amp ifier Buffer amplifier (a -
Linear amplifier Logarithmic amplifier Sguare root extractor Linear bridge Signal converter Sum / difference amplifier Function generator
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Croup II - Pouer Supply Hodules System pouer supply (*
Detector power supply Auxiliary pouer supply Group III - Test Modules Source range test Internediate range test Power rance test Teraperature test Flow test Pressure test (,)
Contact monitor test Group IV - 1.or,1c Modules
(*
,Bistabic Contact monitor Croup V - Relay Modules
~
Auxiliary relay (#}
Reactor trip assembly Contact buffer (b)
Logic buffer (b)
Logic test (b)
Unit control (b)
Trip logic (b)
- (*) Modules that are interchangeable betwect the NI/RPS and the SFAS.
(b) Modules associated only with the SFAS (codules associated only with the NI/RPS have no indicator).
Detectors Pressurc,(Foxboro)
Pressure (Motorola)
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Differential Pressure (Bailey)
Tenperature (Rosemount Model- "?7 CX, JD, and H)
Pressure Switch (Mercoid)
Neutron Detectors Therefore, the seismic and environmental qualifications of the remainder of the Class IE equipment in an cPplication.must be reviewed separately.
6.
The individual applications must demonstrate that the equipment will _
comply to the following interface criteria in its as installed condition:
The still air temperature of the equipment must be maintained.within a a.
ranga of 40 to 110 F at relative humidities of 50%.
b.
The interconnecting wiring and connectors nust be qualified to meet the environmental and scismic plant design criteria.
The electrical pouer sources for the instrumentation shall maintain c.
input to the cabincts of 107 to 127 Y ac at 58 to 62 !!z.
d.
The appl $ cant's Chapter 15 analysis shall be based on assumed crrors for th.c following equipment which are not 1 css than those
' ' listed herein:
(1) Reactor Coolant Pressurc Foxboro Equipment f 1.85%
Motorola Equipment 1 3.69%
(2) Reactor Coolant Flou i 3.0%
(3) Reactor Coelant Temperature j,- 1.0%
(4) Reactor Coolant Pump Status
+ 0.88%
Monitor (5) Reactor Building Pressure
+1.0%
-50%
(6) Neutron Monitoring Total Flux i 4.0%
Flux 1mbalance 1 5.0%
If Motorola Pressure sensors arc used, the technien1 specifications c.
shall require calibration not less frequently than once every four months.
f.
The analysis in Chapto-15 of th~c Safety Analysis Report shall be '
based on assumed resps.ase times which are equal to or greater than q
-4'.
J the following times required for a response to 99% of the differential change from a step input:
(1) Pressure Detectors 250 msec.
(2) Differential Pressure 250 msec.
Detectors (Flow)
(3) Temperature Detectors Models 5 sec*
177 GX and JD Model 177 11 3 sec*
- time to change 63.2% of applied step change in input (4) Prcamplifier 100 ns rise time (5) Count rate amplifier 400 s 0 '0.1 11z 1 s 0 106 };z (6) Ratelof-change amplificr
<10s (7)' Euffer amplifier 50 ms, 1 s (8) Linear amplifier 50 ms (9) Logarithmic acplifier 10 s 0 IJ f A
~
0.1 s 0 10.3 A (10)
Square root extractor Incr 250 ms Deer 500 ms (11) Linear bridge 10 as (12)
Signal converter 300 ms (temp output)'
(13)
Signal converter 300 ms (press. output)
(14) Sum / difference amplifier E
10 ms out Scaled E 10 ms o
(15)
Function generator Slope 15 ms m.
,/
-5
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(16) Bistable
/ 100 ms (17) Reactor Trip 30 ms (ii.terlock or test trips)
(18) Contact Buffer Modules 40 ms energize de-energize 100 ms (19) Logic Buffer Module 10 ms y
(20) Unit Control Module Trip 50 ms g.
Tius applicant shall provide reactor coolant pump status monitors and dctectors,which shall have a combined accuracy of 0.88% and a 4
response time of 6 as or Icss.
s h.
The applicant shall provide a description of and procedures for testing to nst;ure that the equipment is more accurate than and responds in a shorter ti.c than the limits presented in req'uircments (d),
(f), and (g) above.
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