ML18053A683
| ML18053A683 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/22/1988 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18053A680 | List: |
| References | |
| EA-A-PAL-88-020, EA-A-PAL-88-20, NUDOCS 8812060097 | |
| Download: ML18053A683 (13) | |
Text
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ENCLOSURE 3 Consumers Power Company Palisades Plant Docket 50-255 December 1, 1988 CALCULATION OF LOOP ACCURACY DURING VARIOUS ACCIDENT SENARIOS-RADIATION MONITORING 12 Pages 0Cll88-0207-NL02
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PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORKSHEET EA - A-PAL 0=2..:..0 __ _
Sheet __ 1'---- of __ 8 __
Title Calculation of loop accuracy during vari.ous accident senarios-Radjation Monitoring.
INITIATION AND REVIEW 1n1t1ated 1n1t1ator Review Method Chec1c (/)
Technically Reviewed Reviewer Rev Appd Alt Det Ou$11*
Appd If.
By Date By Date Description By Cale RllW Test By 0
Original Issue
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P'A~,,,~ II Jz~Lfi 1f"dlr¥ See the attached sheets 2-8 for Analysis.
Form 3619 9-87
REFERENCES
- 1. A-PAL-88-020 EA-A-PAL-88-020 Page 2 of 8 R
-.1 t:Y. U
- 2.
EA-Cable-26-87-01, Evaluation of IR Changes on the Accuracy of RE-1805, 1808
- 3. Vendor Drawing J52 Sh 87, Test Procedure for High Range Area Monitoring System RP-2A/RD-8
- 4.
Vendor Drawing J52 Sh 83
- 5.
E-48 Sh 3, Palisades Temperature Curves
- 6.
Tech Spec Surveillance Procedure RI-86G, High Range Containment Monitoring Calibration OBJECTIVE This analysis will provide documentation and/or calculation of instrument loop inaccuracies for selected containment and secondary radiation monitoring systems during various events.
The monitoring systems to be evaluated are:
- 1. Containment Radiation (RE-1805, RE-1806, RE-1807, and RE-1808)
- 2.
High Range Containment Radiation (RE-2321 and RE-2322)
- 3. Hain Steam Line Radiation (RE-2323 and RE-2324)
- 4.
Slowdown Radiation (RE-0707)
- 5. Off Gas Radiation (RE-0631)
The different events tQ be evaluated are:
- 1. Normal Operation
- 2.
Small Break LOCA
- 3. Large Break LOCA
- 4. Hain Steam Line Break (HSLB - Inside Containment)
S.
Hain Steam Line Break (HSLB - Outside Containment)
ASSUMPTION By use of engineering judgement analysis EA-Cable-26-87-01 also concludes that Radiation Monitor System accuracy is not significantly effected due to contain-ment cable IR losses during normal operation or small break LOCA events.
IR losses of the additional cable length from the containment to the control room also have no significant effect on the ra.diation monitors accuracy, as cables outside containment are not affected during any of the above events.
METHODOLOGY The errors can be calculated for the systems by dividing the errors up by component:
EL
= Error of the loop ERE = Error of the radiation element ERIA = Error of the radiation indicator Ee
= Error due to IR losses. in the cable ER
= Error due to readability EA-A-PAL-88.,..020
EA-A-PAL-88-020 Page 3 of 8 R;~. o Because the radiation indicators are logarithmic scales, the published errors apply to a percentage of reading.
Errors can not be converted to engineering units because of the logrithmic scale.
The following formula shall be used to calculate the Loop Error:
EL=+/- ((EaE2 + EarA2 + Ec2 1"5 + Ea)]
CONTAINMENT RADIATION MONITORING SYSTEM The Containment Radiation System contains four identical loops (RE-1805, 1806, 1807, and 1808).
A calculation will be performed for RE-1805 that will be applicable to all four.
It must be noted that these errors are calculated for the loop which includes the indicator, not the loop which includes the CHP trip device.
The loop consists of three components which contribute to the loop in accuracy.
They are the radiation element (RE-1805), the radiation indicator (RIA-1805) and the cable between the two.
The RE is located inside the con-tainment and the RIA is located in the mild environment of the control room.
The cable between the two is located both inside and outside of the contain-ment.
Note:
It has been concluded in Reference 2 that a small break LOCA would not.
create significant. temperature or pressure changes.
With this, Reference 3 is' applicable during both normal operations and a small break LOCA
- The radiation indic~tor spans seven decades from 10-2 R/HR to 10+4 R/HR.
The set point for containment isolation is 10 R/HR and the meters are used by the operators up to the 10+2 R/HR decade.
Calculations of accuracy will not be performed above the 10+2 R/HR decade.
Normal Operation and Small Break LOCA A test*procedure (Reference 3) was performed on a RE and RIA combination by the
- vendor.
This test indicates that the RE and RIA combination, under normal
. operating conditions is accurate to +/- 3%. This test did not include a signi-ficant length of cable between the RE and RIA.
As stated in the Assumption, during normal operation, IR losses of the cable will have no significant effect on the meter's accuracy.
Thus Ee= O.
The readability of the meter is to the nearest division,.which is 10% of the full scale for each decade.
The error can be computed as follows for normal operating conditions:
EA~A-PAL-88-020 EL=+/- [(32 )* 5 + 10]
= +/- 13%
Large Break LOCA EA-A-PAL-88-020 Page 4 of 8 R2V. D In the event of a large break LOCA, only items inside the containment will be adversely affected by the event.
Reference S shows the worst case temperature resulting from a large break LOCA would be approximately 280°F.
Table 2 of Reference 24shows that the IR loss of the cable for this temperature would create a 10 R/HR error in the high direction. This means this error is so extremely large that the radiation element and indicator errors do not have to be included.
This meter will read extremely high in the event of a large break LOCA.
Main Steam Line Break (Inside)
During a main steal!l line break, the temperatures inside the containment will reach a peak of 380°F. Reference 2 once again provides a large 10 R/HR error at this temperature. Therefore, other system components are not considered and the instrument will read extremely high in the event of MSLB inside the contain-ment.
Main Steam Line Break (Outside)
None of the system components or cable are located in areas which would be effected by a steam line break outside of the containment.
Therefore, system errors for this case would be the same as errors for normal operation.
Note:
The cables for the following systems have not been considered in loop accuracy.
The cables contribute a very small part to the loop accuracy.
Taking into account conservatisim in test results and calculations, the cable contribution can be ignored, ie, Ee = O.
HIGH RANGE CONTAINMENT RADIATION MONITORING SYSTEM The High Range Containment Radiation Monitoring System consists of two identi-cal loops (RE-2321 and RE-2322).
A calculation will be performed for the RE-2321 loop which will be applicable to both loops.
The loop consists of two elements which contribute to the accuracy, the Radia-tion Element (RE-2321), and the Radiation Indicator (RIA-2321).
The radiation element is located in the containment and the indicator is located in the control roomo Note:
It has been concluded in Reference 2 that a small break LOCA would not create significant containment temperature or pressure changes.
With this, Reference 6 is applicable to both normal, and small break LOCA.
MSLB.outside the containment will also have no significant effect on the containment temper-ature and pres.sure and the MSLB' outside containment will have the same accuracy as. normal operation
- EA-A.:.PAL-88-020
Normal Operation, Small Break LOCA and MSLB (Outside)
EA-A-PAL-88-020 Page 5 of 8 Rc:v'. o The radiation element is Victoreen Model 877-1 and the radiation indicator is Victoreen Model 842-11.
The accuracy of the system under these conditions has been derived from Tech-nical Specification Surveillance Procedure RI-86G.
The procedure states two components of system accuracy; that of the radiation element, and that of the indicator (calibrated accuracy including readability)~
The element is +/- 10% accurate and the indicator is +/- 10% accurate.
The accu-racy of the loop can be calulated as:
E1 = +/- [ERIA2 + ERE2 1"5 E1 = +/- [102. + 102]*5 E1 = +/- 14.1%
Round up to +/- 15%
Note: Testing performed on this system by Victoreen is documented in Test Report 950.301 (E-48 Sh.6DD).
This report applies to both Large Break LOCA and MSLB inside the containment.
Large Break LOCA and MSLB (Inside)
The above referenced test report documents the accuracy of the tested system to be +/-36%.
As shown in EEQ package RE-2 (M-165 Sh.42), the tested configuration bounds the Palisades requirements.
Note:
Because of the location (outside of containment) of the components in the following systems, small break LOCA, large break LOCA and inside the contain~
ment MSLB all have no affect on the accuracy beyond the normal accuracies.
Therefore, for the following systems the accuracies are the same for normal, large break LOCA, small break LOCA and MSLB (inside cont_ainment) events.
EA-A-PAL-88-020
MAIN STEAM LINE RADIATION MONITORING SYSTEM EA-A-PAL-88-020 Page 6 of 8 RciO The Main Steam Line Radiation Monitoring System contains two identical loops (RE-2323 and RE-2324).
A calculation will be performed for the RE-2323 loop which will be applicable to both loops.
The loop consists of two elements which contribute to the accuracy, the radia-tion element (RE-2323) and the radiation indicator (RIA-2323).
The radiation element is located on elevation 607 CCW (Room 123), and the indicator is located in the control room.
Normal Operation, Large Break LOCA, Small Break LOCA, MSLB (Inside)
The radiation element is Victoreen Model 910670 and the radiation indicator is Victoreen Model 842-11.
The indicator has two errors, one associated with its published accuracy and one associated with its readability.
The readability of the meter (842-11) is to the nearest-division, which is +/- 20% (meter has five divisions per decade).
The published accuracy of the meter is +/- 2% (per Victoreen Manual 460007183).
The accuracy of the radiation element 910670 is+/- 20% (per Attachment 1, Record of Telecon with Victoreen).
To calculate the loop error:
MSLB Outside EL = +/- [{ERE2 + ERIA2)" 5 + ER]
= +/- [{202 + 22)* 5 + 20]
= +/- 20.1 + 20 = +/- 40.l Round up to 41%
Due to the location of the Radiation Monitor (607'CCW Room, the elements will be exposed to the high temperature of 279a, and 100% humidity.
This is a standard service radiation element and must be considered to fail during such extreme temperature.
Note: The following systems are located in areas which will not be affected by any of the listed in the objective events.
The normal operating accuracies shall apply to ALL events
- EA-A-PAL-88-020
SLOWDOWN RADIATION MONITORING SYSTEM EA-A-PAL-88-020 Page 7 of 8 RE(.0 The Slowdown Radiation Monitoring System continues one loop, RE-0707.
The loop c consists of two components which contribute to the loop accuracy, the radiation element (RE-0707) and the radiation indicator (RIA-0707).
The radiation element is located in the Turbine Building on 590' elevation and the radiation indicator is located in the control room.
Normal Operation The radiation element is Victoreen Model 843-3 and the radiation indicator is Model 842-1.
The indicat.or has two errors, one associated with its published accuracy, and one associated with its readability. The readability of the meter (842-1) is to the nearest division, which is +/- 20% (meter has five divisions per decade).
The published accuracy of the meter is +/- 2% (per Attachment 2, Victoreen Operator Instructions).
The accuracy of the radiation element (1843-3) is +/- 10% (per Attachment 1, Record of Telecon With Victoreen).
EL = +/- [(ERE
+ ERIA >* 5 + ER]
= +/- [104°5 + 20]
= +/- 30.2 2
2 Round to +/- 31%
OFF GAS RADIATION MONITORING SYSTEM The Off Gas Radiation Monitoring System contains one loop (RE-0631).
The loop consists of two components which contribute to the loop accuracy, the radiation element (RE-0631) and the radiation indicator (RIA-0631).
The radiation element is located in the Turbine Building on the 590' elevation and the radia tion indicator is located in the control room.
Normai Operation The radiation element is Victoreen Model 943-25 and the radiation indicator is 942-100.
The indicator (942-100) is digital and has only one error, which is +/- 1% (per Attachment l, Telecon With Victoreen).
The accuracy of the radiation element (943-25) is +/- 10% (Attachment 1, Record of Telecon with Victoreen)
- EA-A-PAL-88-020
The loop error can be calculated:
= +/- 10.1 Round to +/- 11%
CONCLUSIONS EA-A-PAL-88-020 Page 8 of 8 R£v.D This analysis has provided the calculation* of accuracy error for containment and secondary radiation monitoring systems. summarizes the results of the calculation.
EA-A-PAL-88-020
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Description Containment Radiation Containment Radiation Main Steam Line Radiation Slowdown Radiation Off Gas Radiation Loop RE-1805 RE-1806 RE-1807 RE-1808 RE-2321 RE-2322 RE-2323 RE-2324 RE-0707 RE-0631 E-PAL-88-020
{<.elf. D Small Break Large Normal LOCA Break 13 13
> 100 15 15 36 41 41 41 31 31 31 11 11 11 Note: All accuracy valves are in percent of reading.
- EA-A-PAL-88-020 MSLB MSLB Inside Outside
> 100 13 36 15 41*
>100 31 31 11 11.