ML19329B843
| ML19329B843 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/17/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUDOCS 8002060853 | |
| Download: ML19329B843 (5) | |
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TOPICAL REPORT EVALUATION d);
j Reportthumber:
BAW-10003 Revision 4 (Non-Proprietary)
Report
Title:
Qualification Testing of Protection System Instrumentation Report Date: April 1975 Originating Organization:
Babcock and Wilcox, Company Reviewed By:
Section A - Electrical, Instrumentation and Control Systems Branch, Division of Technical Review Sumary of Topical Report The topical report presents the results of the scismic and environ =cntal qualification testing of the protection system instrumentation uscJ in Babcock and Wilcox nuclear secas systems including:
detectors, signal conditioning instru=entation, power supplies, test signal generators, and relay logic.
Sumary of Regulatory Evaluation As a result of our revicu,'we have concluded that this topical report provides satisfactory ansucrs to the questions which vere trans=itted as a result of our revicu of Revisions 2 and 3 and is therciore aa acceptable basis for the qualification of sc=c equipntent in older plants.
Sur= nary. of Reaulatory position 1.
The subject report in its present form provides an acceptabic basis for testing instrunents and control devices to demonstrate the capabilit*/
of'this equip =ca:. 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, abnor :al, and accident circumstances throughout which the instrumentation must perforn.
2.
The testing uhich is presented in the subject report does not satisff
'all of the requirc=cnts of IEEE Std 323-1974, which was published February 23, 1974 and can not be used as a basis for licensing plants docketed for a construction permit after that date.
3.
BAW-10003 Revision 4 cay be used as a basis for licensing plants in viich construction pcrait second round questions were issued prior to l
April 30, 1974.
4.
The subject report is not applicable to solid state logic systems such as RPS-II.
t 5.* The subject report is only applicabic to the following portions of the reactor prote'etion system:
Group I - Amplifier Modules Preamplifier
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Count rate amplifier 8002060
4
.s 2,
o Rate-of-change amplifier Baffer emplifier(a)
Linear amplifier Logarithmic a=plifier Square root extractor Lincar bridge Signal converter Sum / difference amplifier Function generator Croup II - Pouer Supply Modules System pouer supply (*}
Detector power supply Auxiliary power supply Croup III - Test Modules Source range test Intermediate range test Power rance test Teraperature test Flow test Pressure test (,)
Contact monitor test Group IV - Logic Modules
,Bistabic "
Contact monitor Croup V - Relay Modules Auxiliary relay ("}
Reactor trip assembly Contact buf fer (b)
Logic buffer (b)
Logic test (b)
Unit control (b)
Trip logic (b)
I") Modules that are interchangeabic between the NI/RPS and the SFAS.
0 ) Modules associated only with the SFAS (codules associated only with the NI/RPS have no indicator).
Detectors Pressure,(Foxboro)
Pressure (Motorola)
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Differential Pressure (Bailey)
Temperature (Rose =ount Models 177 CX, JD, and H)
Pressure Switch (Mercoid)
Neutron Detectors Therefore, the scismic and environmental qualifications of the rc=sinder of the Class IE equipment in an application.must be reviewed separately.
6.
The individual applications cust demonstrate that the equip =cnt 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.
range of 40 to 110"F at relative humiditics of 50%.
b.
The interconnecting VUring and connectors must be qualified to racct the environ =cntal and scismic plant design criteria.
The electrical power sources for the instrumentation shall maintain c.
input to the cabinets of 107 to 127 V ac at 58 to 62 Hz.
d.
The applicant's Chapter 15 analysis shall be based on assu=cd
, errors for the following equip = cut which are not 1 css than those listed herein:
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(1) Reactor Coolant Pressure Foxboro Equip =cnt 1 1.85%
Motorola Equipeent i 3.69%
(2) Reactor Coolant Flou i 3.0%
(3) Reactor Coelant Te=perature j; 1.0%
(4) Reactor Coolant Pu=p Status 1 0.88%
Monitor (5) Reactor Building Pressure
+1.0%
~50%
(6) Neutron Monitoring Total Flux i 4.0%
Flux I= balance j; 5.0%
If Motorola Pressure sensors are used, the technical specifications e.
shall require calibration not less frequently than on~ce every four Months.
f.
The analysis in Chapter 15 of the Safety Analysis Report shall be based on assu=ed response ti=es 'which are equal to or greater than 4
f 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 msce.
Detectors (Flow)
(3) Temperature Detectors Models 5 sec*
177 GX and JD Model 177 !!
3 sec*
- time to change 63.2% of applied step change in input (4) Preamplifier 100 ns rise ti=c (5) Count rate amplifier 400 s 0 'O.1 11a 1 a 0 106 11 :
(6) RateJof-change a:plifict
< 10s (7)
- P,uf fer amplifier 50 ns, 1 s (8) Lincar amplifier 50 ms (9) Logarithmic a=plifier 30s010"f1 A
3 0.1 s 0 10 A
(10)
Square root extractor Incr 250 ms Decr 500 cs (11) Linear bridge 10 ms (12)
Signal converter 300 ms (temp output)
(13)
Signal converter 300 ms (press. output)
(14) Sum / difference a=plifier E,,g 10 ms Scaled E 10 ms (15)
Function generator Slope 15 ms
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(16) Bistable
/ 100 ms (17) Reactor Trip 30 ms (interlock or test. trips)
(18) Contact Buffer Modules energize 40 ms de-energize 100 ms (19) Logie Buffer Module 10 ms (20) Unit Control Module Trip 50 ms g.
The applicant shall provide reactor coolant pu=p status monitors and detectors which shall have a combined accuracy of 0.88% and a response tice'of 6 as or 1 css.
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h.
The applicant shall provide a description of and procedures for testing to assure that the equipment is more accurate than and responds in a shorter time than the limits presented in req'uirements (d),
(f), and (g) above.
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