1-2-unc-421 calc1, rev. 0, 'post-accident high range … · 2017-06-29 · 1-2-unc-421 calc1...

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. . l!'i'f!' AMERICAN" iiliil EU"1l1C

l'OWEll. .1!1'.c..m..-._,, __

CALCULATION NO.:

SAFETY RELATED:

COOK NUCLEAR PLANT CALCULATION COVER SHEET

1-2-UNC-421 CALC1 REVISION: 0

IZ!Yes O~o UNIT NO.: 1.& 2

SYSTEM FUNCTIONAL CALC: IZ!Yes 0No SYSTEM: RMS

Page I of "10 ,~J '"'" 'l'I

TITLE: Post-Accident High Range Containment Area Radiation Monitoring Loop Uncertainty Calculation

REASON FOR REVISION: Initial Isstie File: U421-10a.doc The total indication uncertainties determined in this calculation supersede the total uncertainty portions of ECP l-2-V2-0l CALCl, Rev. 4 for EOP functions for the instruments listed in Section 1. This calculation revision is being issued because ECPs 1-2-V2-1 CALCl, Rev. 4 has not been documented as acceptable for unrestricted use.

Are there any assumptions that require later verification?

Are there any limitations associated with the use of this calculation? (Specify) See Section 8.2

AEPNG FUNCTIONAL AREA: NEIC

0Yes IZ!No

IZ!Yes 0No

~----------~

CALCULATION STATUS: Unrestricted __)_{__ Restricted Not Statused Superceded Void

Impact Assessment CR(s):

PREPARED BY:

W_ H. Powell Print Signature ·

REVIEWED BY:

N. R. Ramiro Print Signature

Review Method: [8J Detailed Review- · D Alternate Calculation

APPROVED BY (Manager or Designee): "1- . JK.

~ ~ Plint . . ·.. . Slgnatnr~.

Hold

10/3/99 Date

Date

Date

Project No. 10597-112

Calculation No. l-2-UNC-421 CALCl Re\•ision:O

Table of Contents

Cover Sheet

Multiple Preparers/Reviewers

Table of Contents

I. Purpose/Objective

2. Design Inputs

3. References

4. Methodology

5. Acceptance Criteria

6. Assumptions and Limitations

7. Calculation

8. Conclusions

9. Recommendations

10. Attachments:

A. Walkdown Information

B. Victoreen Containment Monitor Qualification Test Plan, Test Report 950-301, Addendum I, Section IV

C. Information Management System (IMS) Reccuring Maintenance Planning for l-VRA-1310, l-VRA-14I0;2-VRA-2310and4-VRA-2410, viewed on 7/15/99.

Attachment I - Calculation Impact Assessment

Attachment 2 - Review Comment Form

Page No. Sub-page No.

2

3

3

4

11

13

16

16

18

22

23

23

4 pages

3 pages

4 pages

:3 pages

,3page~


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Calculation No. l-2-UNC-421 CALCl Revision:O Page3

1. · PURPOSE I OBJECTIVE

The purpose-of this calculation is to detennine the total loop uncertainty for the Post- Acci~ent High R.aJ:ige Containment Area Monitor ineter, and to establish a· setpoint for the alann to confinn that the limiting Tech. Spec. radiation levels are not exceeded: This calculation is to be used as input to ECP 1-2-00-14. These uncertainties are applicable in the Emergency Operating Procedures (EOPs), Footnote Nos. T.05 and T.06, for the following instrument loops (See Section 2.1 for loop configuration):

Detectors 1-VRA-1310 l-VRA-1410 Readout Modules l-VRA-1310-C~ l-VRA-,1410-CRI

2-VRA-2310 2-VRA-2410

2-VRA-2310-CRI 2-VRA-2410-CRI

Errors are detennined for accident environmental conditions only (refer to Section 4.1 ).

Assumptions and limitations associated with this calculation are id,entified in Section 6.

This calculation has been classified as safety-related iri accordance with the classification of at least one of the applicable instruments in the Facilities Database (Ref. 3.4.1).

The total indication and alann uncertainties determined in this calculation supersede the total uncertainty portions of ECP l-2-V2-01 CALC 1 for EOP functions for the instrument loops listed above. This calculation revision is being issued because ECP l-2-V2-0l CALCl, Rev. 4 has not been documented a5 acceptable for unrestricted use.

This calculation is for as-built conditions.

Pr~ject No. 10597-112

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Calculation No. I-2-UNC-421 CALCI Revision:O Page4

2. DESIGN INPUTS

2.1 INSTRUMENT LOOP CONFIGURATION

Tlie "f-9nowihg block diagram was. deve~p~d based on drawings OP-1-98815 and OP-2-98815 (Ref. 3.5.3 and.3.5.4).

Inside Containment Outside Containment

DETECTOR READOUT MODULE VRA-1310 ~ VRA-1310-CRI ...

Meter & Alarm Functions

Typical for all loops

l-VRA-1310* l-VRA-1410** 2-VRA-231 O* 2-VRA-2410**

l-VRA~l310-CRI* l-VRA-1410-CRI** 2-VRA-2310-CRI* 2-VRA-2410-CRI**

The Readout Module Model 876A- l is a logarithmic microammeter that covers six decades of radiation intensity. It utilizes integrated circuits, printed circuit boards, relays and other common· electronic equipment It provides the high voltage required as the-collection volt.age for the Detector (Model 877-1 ). A number of alarm functions and relay outputs are provided. A recorder and computer output is also provided.

Notes: 1. '(*) - Instrumentation powered from Train "A".

(**)-Instrumentation powered from Train "B". 2.


Calculation No. l-2-UNC-421 CALCl Revision:O Pages

2.2 INSTRUMENT LOCATIONS I ENVIRONMENT

The instrument location information and applicable environmental conditions are defmed in the sections below.

2.2.l Primary Element NA

2.2.2 Sensors (Radiation Detectors)

The radiation detectors 1-VRA-1310, l-VRA-1410, 2-VRA-2310 and 2-VRA-2410 are located inside Units 1 & 2 containments, respectively,' per the FacilitY Data Base (Ref. 3.4.1), and per Drawings: 1-55701 (Ref. 3.5.9), 1-5104G (Ref. 3.5.5), 2-55701 (Ref. 3.5.10) 2-5104G, (Ref. 3.5.6) and SCEW sheets (Ref. 3.3.1).

..

The purpose of this calculation is to determine the accident errors. Therefore, in accordance with · Section 4.1, the environmental conditions associated with EOP accident environmental conditions inside containment are evaluated as defined below.

Parameter Accident (Section 3.8.1 and Ref. 3.3.1)

Minimum Temperature 50°F Normal Temperature 120°F Peale Temperature 240°F Peale Pressure 28.3 psia (Unit 1 ), 29 .1 psia (Unit 2) Relative Humidity 100% Radiation SOMrad

2.2.3 Converters and Indicators (Readout Module)

The high range area radiation readout modules: 1-VRA- 1310-CRI, 1-VRA- 1410-CRI, 2-VRA-2310-CRI, 2-VRA- 2410-CRI are located in the control room, per Facility Data Base System (Ref. 3.4.1), and drawings OP-1-98815 (Ref. 3.5.3) and OP-2-98815 (Ref. 3.5.4).

. . .

Per Reference 0 and S~ction 6.1.2.2, the environmental ~oriditions inside the control room for indicators or recorders ·are considered controlled to Within the specifications below under accident operating conditions~ .· · · · .

Parameter Control Room Environment for lndictors or Recorders ·.

Temperature .· · 5.S to 104°F Humidity 25 to 80%RH


Calculation No. l-2-UNC-421 CALCl Revision:O .

2.3 INS1RUMENT MANUFACTURER MODEL NO. ·

The manufacturer and model number infonnation for the instruments in this calculation are provided in the table below.

Loop Equipment No. Manufacturer Model No. Reference Component Radiation 1-VRA-1310 Victoreen 877-1 SCEW Sheet (Ref. 3.3.1) Detector l-VRA-1410

2-VRA-2310 2-VRA-2410

Radiation 1-VRA-1310-CRI Victoreen 876A-l Elem Diag (Ref. 3 .5 .3 and Readout 1-VRA-1410-CRI 3.5.4) Module 2-VRA-2310-CRI

2-VRA-2410-CRI

2.4 CALIBRATION INFORMATION

2.4. l The following table summarizes the calibration parameters utilized in calibration procedme 1IBP6030.IMP.311, (Ref. 3.2.4).

Loop Component Equipment No. Input Span Output Span I Tolerance Radiation Detector l-VRA-1310 Source Point check only. Source Point check only;

I Tolerance- ±10%. Radiation Readout l-VRA-1310-CRI 6.90x.10-u to 6.90xl0-" lxlOu to lxlOu (Rib)/ Module (Amps) Tolerance- ±2 needle widths

These parameters are typical for"the loops: l-VRA-1410, 2-VRA-2310 and 2-VRA-2410 (Refs. 3.2.5, 3.2.6 and 3.2.7, respectively). The calibration interval for the instruments in these loops is 18 months per Tech. Spec. Table 4.3-3, Amendment 189 and Table 4.3-3, Amendment 175, (Ref. 3.2.2). A late factor of25% is applied to this interval in accordance with Technical Specification 4.0.2 (Ref. 3.2.2). To account for post-accident drift, an additional 4 months is included per the S_CEW Sheets (Ref. 3.3.1). Therefore, the total drift intenial is

DI = 18 months * (1 + 25%) + 4 months DI = _26.5 months -


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Calculation No. l-2-UNC-421 CALCJ Revision:O

2.5 PROCESS

2.5.l Process Measurement Ert:ects (PMEb)

Per Assumption 6. J .6 and Ref. 3. 7 .1, the Process Measurement Effects are included in the specification for the reference accuracy. Therefore,

PMEb=O

2.5 .2 Primary Element Effects (PEEb)

There is no primary element. Therefore,

PEEb=O

2.6 SENSOR INPUTS (RADIATION DETECTOR)

TAG NUMBERS: l-VRA-1310, l-VRA-1410 (2.1] 2-VRA-2310, 2-VRA-2410

MANUFACTURER: Victoreen [2.3] MODEL NO.: 877-1 [2.3]

INPUT SPAN: lx10° to lxl06 (R/h) [2.4] OUTPUT SPAN: 6.90x10·11 to6.90x10·5 (Amps) [2.4]

Per AttachmentB and Ref. 3.7.l, the 877-1 Detector and 876A-1 Readout Module are known collectively as High Range Containment Monitor 875. This "monitor" has the following System Accuracy:

Accumulative @Meter: ±36% ofinput radiation (See Attachment-B).· · Analog outputs; . ±28% of input radiation (See Attachment B)

Per Attachment B, these are cumulative errors caleulated using the sum of the deviations of the component em)~ associated with the detector, amplifier and meter (where applicable). Component error8 include extreme temperature and liumidit)r effects, voltage variation effects, radiation and thermal aging, permanen(vibration or seismic effects and LOCA environment effects. Since the errors associated with the Detector are included in the accumulative accuracy of ±36% for the Monitor, all detector uncertainties (i~e.,_ CA, MTE, DR. TE, HE, ·PSE, EAb, Seb and IR) are considered in the Monitor accuracy. · ·

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Calculation No. l-2-UNC-421 CALCl -Revision:O Page8

2. 7 INDICATOR INP"£!TS (READOUT MODULE) .

This device is· designated as Radiation Readout Module. It consists of a Meter: and Alarm outputs. · · ·

TAG NUMBERS:

MANUFACTURER: MODEL NO.:

INPUT SPAN: OUTPUT SPAN:

2.7. l Calibration Accuracy (ICA)

l--VRA-1310-CRI, l-VRA-1410-CRI [2.l] 2-VRA-2310-CRI, 2-VRA-2410-CRI Victoreen [2.3] 876A-I [2.3]

6.90xl0"11 to 6.90xl0"5 (Amps) [2.4] lxl0° to lxI<)6 (R/h) [2.4]

Per Attachment B (Ref. 3. 7. l ), the reference accuracy of this device is

IRAM = ±36% setting (Meter) IRAA = ±3% setting (Alarm)

Per Section 2.4, !be calibration as left tolerance (IAL 1) of the meter and the alarm is ±2 needle widths (Ref. 3.2.4). Per Assumption 6.1.7, ±2 needle widths is equal to± 5% of setting. Therefore,

IALTM =± 5% of setting JAL TA = ± 5% of setting

Since IRAM > JAL TM. the IRAM is utilized as the calibration accuracy for the meter, and since IRAA <JAL TA, the IAL TA is utilized as the calibration accuracy for the alarm, in accordance with Section 4.4. Therefore,

ICAM = ±36 % setting (Meter) - ICAA · "".' ±5% setting (Alano)

2.7.2 M&TE(IMTE).

Per Assumption 6.1.8, the M&TE equipment used to ealibrate the meter is considered 4 times more accurate than the meter itself. Therefore, . · ·- ' ·

. IMTEM = ±9 % setting(Meter)

The M&TE error effect for calibrating the 1tlarm is considered equal to ·the reference accuracy (IRA) in accordance with Section 4.5. Therefore, · · ·

IMTEA = ±3 % settmg (Alarrfi)


Calculation No. l-2-UNC-421 CALCZ Revision:O

2.7.3 Drift (IDR)

. The vendor does not provide specifications for the drift effects. In accordance with Section 4.7, the drift is setequai to reference accuracy. ··Therefore, · . ·

. . ID~ = ± 36% setting·(Meter) IDRA = ± 3% se~ing (Alann)

2.7.4 Temperature Effect (ITE)

. Per Attachment B (Ref. 3. 7. I), the temperature effect is included in the specification for the reference accuracy. Therefore,

ITEM = 0% (Meter) !TEA = 0% (Alann)

2. 7 .5 Humidity Effect (IIIE) Per AttachmentB (Ref. 3.7.1) and the assumption in Section 6.1.S, the humidity effects are included in the specification for the reference accuracy. Thus,

IHEM = 0% (Meter) setting IHEA = 0% (Alarm) setting

2.7.6 Power Supply Effect (IPSE)

Per Attachment B (Ref. 3.7.1) and the assumption in Section 6.1.5, the power supply effects are included in the specification for the reference accuracy. Thus, . ·

IPSEM = 0% setting IPSEA = 0% setting{

2.7.7 Resolution (IRES) In accordance with Secti()n 9 .11 of EG-IC-004 (Ref. 3 .1.2),. the indicator resolution is considered 1/2 the minor division on the scale of the indicator. Per calibration procedures (Ref. 3.2.4, 3.2.5, 32.6, and 3i.7), and per Waikdown Sheets (See Attachment A), the minor division of the indicator is 20% efthe setting (20% of decade). Figure 1 of Ref. 3.2.4 thru 3.2.7 shows the ~inor divisions equivalent ~o 20% of each decade. . .. Therefore, ·

IRESM · == ± "1(2 • 20%/setting = ± I 0% setting·

IRESA =NIA.

2. 7.8 Accident Effects (IEA!>)

Accident Effe~ts are not applicable for th.is component bec~tise it is in a mild environment per Section 0. Therefore,

IEA~N/A lEAbA=N/A


Calculation No. l-2-UNC-421 CALCl Revision:O Page lff

-2. 7.9 ·Seismic Effects (ISEb)

Per Section 4.12, Seismic Effects are not applicable for d1is component. Thus,

ISEbM =NIA·. ISEbA =NIA

2. 7. I 0 Insulation Resistance Errors (IIR)

The cable that connects the detector to the monitor is a specially designed cable and any associated uncertainties due to accident environments are included in the vendor specified accuracy per Assumption 6. I .4. The alami cabling is internal to the monitor therefore is not exposed to the abnormal conditions. Therefore,

~ = 0% setting URA =NIA


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Calculation No. l-2-UNC-421 CALCl Revision:O

3. REFERENCES

3.1 METHODOLOGY: .

3.1.l ISA 67:04-Part II-i994, ·~Methodologies fonhe Detennination of Setpoints for Nuclear SafetyRelated Instrumentation."

3.1.2 AEP, EG-IC-004, "I&C Engineering Guide for Instrument Setpoint/Uncertainty," Rev. 3, CS-2.

3.2 AEP PROCEDURES I CALIBRATION INFORMATION

3.2.1 12-E.HP 5040 DES.003, "Calculations," Rev; 2A

3.2.2 Technical Specification, Section 4.0.2, Amendment 190 (Vnit 1 ); Amendment 176 (Unit 2); Table 4.3-3, Amendment 189 (Unit 1 ); Table 4.3-3, Amendment 175 ·(Unit 2)

3 .2.3 Information Management System (IMS) Recurring Maintenance Planning viewed on 7 /15/99 for 1-VRA-1310, 1-VRA-1410, 2-VRA-2310, 2-VRA-2410 (AttachmentC)

3.2.4 ll.HP6030.IMP.3 l l, Calibration of High Range Containment Radiation Monitor VRA-1310, Rev. 3, Change #3

3.2.5 1IHP6030.IMP.312, Calibration of High Range Containment Radiation Monitor VRA-1410, Rev. 3, Change #3

3.2.6 2I.HP6030.IMP.4 l l, Calibration of High Range Containment Radiation Monitor VRA-2310, Rev. 3, Change #3

3.2. 7 2IHP6030.IMP.412, Calibration of High Range Containment Radiation Monitor VRA-2410, Rev. 3, Change #4

3.3 ENVIRONMENTAL REFERENCES.

3.3.1 AEP, System Compo~entEvaluation Work Sheets(SCEW) Sheets: 1-135, Rev. 7;2-135, Rev. 7. . . . . . . . . . . .

3.4 AEP DATABASE REFERENCES

3.4.l facilityDatabasefor the following Components, viewed on 6/24/99.

Detectors 1-VRA-1310 . 2-VRA-2310 . l-VRA-1410 . i-VRA-2410 ·

Readout Module l-VRA-131 O.,CRl l-VRA-1410-CRl

2-VRA-2310-CRI 2-VRA-2410-CRI

Proje.ctNo.10597-112

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Calculation No. I-2-UNC-421 CALCI Revision:O

3.5 AEP STATION DRAWING REFERENCES

3.5.1 PSI-9IOI I, Rev. 4, "Key Plan of Control Room".

3.5.2 PS2-910I I, Rev. 2, "Key Plan ofControrRoom".

3.5.3 OP-1-98815, Rev.3, "Radiation Monitoring System Area Monitors VRA-1310 & VRA-1410 Elementary Diagram". ·

3.5.4 OP-2-98815, Rev.7, "Radiation Monitoring System Area Monitors VRA-2310 & VRA-2410 Elementary Diagram". -

3.5 .5 OP-1-5104G, Rev .5, "Functional Flow Diagram Area Radiation Monitors".

3.5.6 OP-2-51040, Rev.4, "Functional Flow Diagram Area Radiation Monitors".

3 .5. 7 OP- I-5 l04F, Rev .33, "Functional. Flow Diagram Radiation Monitor Unit No. l ".

3.5.8 OP-2-5104F, Rev.34, "Functional Flow Diagram Radiation Monitor Unit No. 2".

· 3.5.9 1-55701, Rev.10, "Location of Radiation Monitors & Detail of Shielded Transport Container".

3.5.10 2-55701, Rev.I I, "Location of Radiation Monitors".

3.6 ECPS, ICPS I CALCULATIONS

3.6.I AEP, ECP 1-2-00-14, "EOP Footnotes Document," Rev. 15.

3.6.2 AEP, ECP I-2-V2-01 CALCI, Rev.4, "Post-Accident High Range Containment Area Radiation Monitoring"

3.7 VENDORINFORMATION

3.7.1 AEP, VTM-VlCT-0001, VTD-VlCT-006, "Victoreen, Inc., Installation, Operation and Maintenance for Model 875 High Range Containment Monitor'' (Pub. 877-1- I G), Rev. 0.

3.8 MISCELLANEOUS REFERENCES

3-8.1- · AEP DIT-B-00 I 90-00,. "Fix Parameters for control r!X>m temperature, control room relative humidity, and Auxiliary Building_temperatures for use in uncertainty calculations", dated September 20, 1999. Scmrce of information: . . . . ~ .

. UFSAR, Calculation MD-l2-HV-002N Rev o' cs 0 290C'i98, DB-12-HV AB-Rev 0 cs 5 26NOV1997, DB-12-HVSRRev OCS l 17MAR1997, DB-12-RHRS Rev 0 CS IO l6DEC1998, DCC-HV-12-CRllN, DcP-681, DCP-275 . . . .

3.8.2 Condition Report: P-99-19726 Vendor Model number for the High Range Containment Area Radiation Monitor. · ·

Project No. I0597-ll2

CalculationNo. l-2-UNC-421 CALCI Revision:O

4. METHODOLOGY

The methodology of this calculation is in accordance with EG-IC-004 (Ref. 3 .1.2). The following sections are provided for clarification of the items discussed.

4.1 EOP NORMAL, AND ACCIDENT ENVIRONMENTAL CONDITIONS This calculation only addresses accident scenarios in which the EOJ>s are utilized. However, the applicable environmental conditions are dependent on the location of the components and are defined by the following categories:

a. EOP normal conditions are defined as the transition point inside containment in which operators are directed to consider containment nonpal conditions versus accident conditions. Normal errors are determined for instruments inside containment based on the effects of EOP normal conditions.

b. Accident errors are determined utilizing the effects of worst case accident conditions for the applicable area.

c.. Control room conditions are considered the same for both normal and accident error determinations.

4.2 COMBINATION OF ERRORS (REFER TO SECTIONS 7.6, 11.1, 12.2, 13.5 OF EG-IC-004) · The combinations of errors are applied uniformly based on the error type (i.e. random dependent, random or bias) as defined below.

Given: Random Dependent Errors: ±A, ±B Random Errors: ±C, ±D, ±E Bias Errors: ±F, G+, ff

Then, the· standard combination errors utilized in accordance with EG-IC-004 and ISA-67.04, is square root sum of squares (SRSS) for random errors and algebraic for biases. Thus, the errors defined above are combined to determine a total uncertainty (TU) as follows:

nr =+cc..\+ B>2 + c2 + o2 + E1>112 + F + o+

ro· ~.:-((A+ B)2 + C2 + D2 + E2)

112 + (-F) +ff

Unless, otherwise noted, the default classification of the error effects typically considered is as ~~ .

Random Dependent: CA, MTE . Random: . PEE, RA, DR, TE, HE, SPE, OPE, PSE, RES, Deadband, Reset, Capillary

· Tubing Effects · · · Bias: PMEb, A TEb, AREb, SEb, IRb.

Notes: 1) standard variable names of errors are used per EG-IC-004



2) errors above are listed whether applicable or not 3) all bias effects are denoted with a lower case b at the end of the variable name.

The specifications that are used to determine an error are considered the same type as the specifieation for that error. For example, CA is based on RA, so if RA is made up· of repeatability, hysteresis, and linearity, then these three terms are combined using SRSS since RA is considered a random error.

All random errors are considered 20 values throughout this calculation. Therefore, no conversion is utilized for sigma levels and all results are based on 2o random errors.

4.3 USE OF l-2-UNC-000 CALCl, ICP-00231

Not applicable for this calculation.

4.4 CALIBRATION ACCURACY (REFER TO SECTION I 0.1.1 OF EG-IC-004)

The Calibration Accuracy (CA) is detennined by comparing the reference accuracy (RA) of a device with the as-left calibration tolerance (ALT) for the device. The larger of these two values is then used as the calibration accuracy. This may be expressed as CA= Max (RA, ALT).

· 4.5 M&TE- GENERAL (REFER TO SECTION 10.1.2 OF EG-IC-004)

The M&TE error effect is conservatively estimated as equal to the reference accuracy of the device being calibrated. This is considered reasonable because it is necessary for M&TE equipment to be more accurate than the device being calibrated in order for the calibration to be effective. In addition, a common guideline is for M&TE equipment to be more accurate than the device being calibrated by a factor of 4: 1.

The use ofM&TE uncertainty equal to the reference accuracy provides a conservative approach and is taken to allow for flexibility in the type of M&TE equipment used for calibration .

. 4.6 INDICATOR OR RECORDER M&TE~D RESOLUTION (RES) During the indicator or recorder calibration. the M&TE for the indicator or recorder is simply the device used to measure the electronic input to the indicator. The M&TE error for this signal is comparable to the M&IB error for the previous device. Therefore, the M&TE error for the indicator or recorder. is estimated as equal to the M&TE error of the previo_us device.

If the reference accuracy of the indicator is smaller than the M&TE error of the previous device, the reference accuracy of the indicator or recorder may be used as the input M& TE error per Section 4.5. · . · ·

. . . .. . . .

If the mdicator or-ree~roer is c~librated using a string calibr~ti~n with other instruments, the input. M&TE error of the string is equal to the M&TE error ofthe-first device in the string. The M&TE error of the first device in the string is consel'Vatively· estimated as equal to the reference accuracy of that device per Section 4.5. ·

The 01,1tput is rilea5ured by.reading th~ indicaror itself. An estimate of this accuracy is included as the resolution (RES) error. This error is estimated as· l/2 the smallest division for analog indicators and as the smallest digit for digital indicators perSection 9 .11 of EG-IC-004. . ·

To account for the potential effect of resolution during operation, the final error estimate is rounded off to the neareSt conservative (i.e. larger) value consistent with the resolution (RES).


Calculation No. l-2-UNC-421 CALCI Revisioa:O

4.7 DRIFT EFFECTS.

Some vendors do not provide specifications for- drift effects. This may be due to a lack of data or -f!iese effects may be included in th.e overall refere1,1ce accuracy specification provided. In general; if no specifications are provided for drift, then the reference accuracy is used as a limit of error for the drift effect. This calculation will not address the calibration interval in these cases.

4.8 TEMPERATUREEFFECTS

Some vendors do not provide specifications for· ambient temperature effects. Typically a range of acceptable operating temperatures is provided. If a range is specified and bounds the normal operating environmental conditions, then the temperature effect may be considered included in the specification for the reference accuracy. If a normal operating range is not provided or unavailable, then the reference accuracy is used as a limit of error for the temperature eff-ect. Note that normal temperature effects are based on the nonnal ambient temperature range and are considered independent of accident temperature effects.

If the vendor specifies an ambient temperature effect, the full range of ambient temperature changes will be used when determining instrument errors to ensure the most conservative error analysis results.

4.9 RACK MOUNTED EQUIPMENT TEMPERATURE For rack mounted equipmen~ an increased ambient temperature is iilcluded in the analysis to account for the effect of heat generated by the equipment in the rack. Per Reference 3 .8.1, typical rack heat-up is 'bounded by a1,1 increase in ambient temperature of 18°F. This effect is applied to all rack mounted equipment. This increased temperature effect, however, will not be included for indicators or recorders in the control room since these deyices are mounted on the surface of a panel rather than inside an enclosed rack and therefore would not be as susceptible to this effect.

4.10 HUMIDITY EFFECTS Humidity effects or limits are generally not specified by vendors. In the case of a harsh environment, testing is performed under anticipated humidity levels. Unless otherwise noted, humidity effects are considered negligible or included in the specification for the reference accuracy.

4.11 POWER SUPPLY EFFECTS

It is considered-s~dard design practice to utilize power supplies that are within the require~ents of the instrumentation'being utilized. If a power supply effect is specified by the vendor, then typical power supply requirements of +/-10% for DC power supplies and +/-10 V A,.C for a 120 V AC power supply may be Lised to determine the power supply effect. · · ·

. If no power supply _effeet.is specified by the vendor, then pow~r supply effects are considered negligible or included in the specificati.ori for the reference. accuracy.

4.12 SEISMIC EFFECTS (REFER TO SECTION 9.10.4 OF EG:.IC-004)

Per Section 9.1 OA ofEO-IC-004~ a s~ismic event coincident with an accident event is considered not applicable. This Calculation addresses EOP accident seenarios only (Section 4~ 1 ). Therefore, seismic effects are not applicable since a seismic event is munially exclusive with an EOP accident condition. · · · · ·

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Calculation No. l-2-UNC-421 CALCI Revision:O

4.13 RADIATION EFFECTS (REFER TO SECTION.9.10.3 OF EG-IC-0~4) Under normal conditions radiation effects are considered negligible or included in the specification for the reference accuracy. This is considered acceptable because radiation levels are typically relativ~ly small and may be caljbrated out under normal conditions such that cumulative effects are ·minimii.ed. Therefore, an error effect due to radiation levels for nonnal conditions is·not included in the normal.errors. The .higher radiation levels associated with accident conditions are addressed as an accident effect

4.14 ACCIDENT EFFECTS (REFER TO SECTIONS 9.10 AND 13.5 OF EG.:IC-004)

Accident effects may be specified as an error effect due to accident temperature, radiation and other individual environmental parameters. Alternatively, an all-encompassing environmental accident effect may be specified. In either case, the accident effects are applied as a bias and combined with the normal error effects where applicable.

4.15 IRERRORS

Not applicable for this calculation.

4.16 OTHER SPECIFICATIONS If other potential error effects are not specified by the vendor and the operating limits associated with the device are not exceeded; then it is considered reasonable to consider such effects as negligible or included in the reference accuracy.

4.17 USE OF VENDOR TECHNICAL DOCUMENTS/MANUALS The vendor technical documents (VTD) and vendor technical manuals (VTM) are utilized where applicable for design input infonnation related to perfonnance characteristics of the instrumentation. The use of the vendor information is validated by ensuring that the model number installed in the plant matches the model number for the vendor catalog information that is used. Therefore~ the use of the vendor information for the purposes of this calculation is considered acceptable.

S. ACCEPTANCE CRITERIA

The acceptance criteria associated with this calculation i~_to _establish a setpoint for the alarm to confinrrthat the'li.miting Tech. Spec. requirement ·radiation level of s;I 0 R/hr is not exceeded . (Ref. 3 .6.1 ). The results are determined for use in accordance with the purpose and methodology.

6. ASSUMPTIONS AND LIMITATIONS

6.1 ASSUMPTIONS·

6.1.1 Methodology Section

.The methodology ~ec~ion describes definitions, th~ generic rules _that are followed and clarifications of how the gilidarice in EG-IC-004 is implemented. The ba5is for these items include engineeringjudgment and assumptions relared to the approach to be taken when vendor information is not specified for certain parameters. These methodology sections are then referred to where required in the applicable design inpu~ sections. In lieu of a re-listing o_f each item in the

ProjectNo. 10597-112 ·

Calculation No. l-2-UNC-421 CALCl Revision:O.

assumptions section, the basis or justification for the approach outlined and the interpretation of · the vendor data is provided in the methodology sections and where applicable, the design input

.. sections them!?elves: Any items that.have a ·pearing on the use of.this calculation, (e.g. a limitation, u.n\'.erified assu~ptic;m) are still liste~ in the assumptions section.

6.1.2 Environmental Conditions

6. 1.2.1 Section Not Used

6.1.2.2 Control Room Conditions

The control room is a controlled environment under both normal and accident conditions. Therefore, for. both normal and accident the specifications are considered the same.

It is assumed that all radiation levels are low or moderate since the area is required for use by personnel and as such will not result in a significant impact on instrumentation in accordance with Section 4.13. ·

6.1.3 Section Not Used

6.1.4 Insulation Resistance

· Per ~ttachment B it is assumed that Insulation Resistance Error

is included in the vendor specification for the reference accuracy.

6.1.5 System Uncertainty

Per Attachment B the cumulative errors are calculated using the sum of the deviations of the component errors associated with the detector, amplifier and meter. Component errors include extreme temperature and humidity effects, voltage variation effects, radiation and thermal ·aging, permanent vibration or seismic effects and LOCA environment effects. Therefore~ it is assumed that these uncertainties are included in the vendor specified reference accuracy of ±36% .

6.1.6 Process.MeasurementEffects

The ion chamber detector is treated as a sensor. The-response of the radiation detector is sensitive to the specific radionuclide present.· Changes in the level of radiation flwc"incident upon the detector and the enviroilment will cause changes in the detector response. Each type of detector has a different resp'?nse to radiation of varying energy. ·However, per vendor test report (See Attachment B), the specified vendor accuracy is in percent of input radiation. It is therefore assumed that the PM effect is included in the ve~dor accilracy term.

Project-No. 10597-112 .


"6.1.7 Calibration-Accuracy .

Per Section 2:4,, the calibration as left tolerance (IAL T) of the meter and the alarm is ±2 needle widths (Ref. 3.2.4). A review of the meter scale drawing (see Attachment A) was performed. When compare~ with Reference 3.2.4, it is assumed that two needle widths is equal to Y2 ofa minor division, over the six decades of the calibrated portion of the span. Yl of a minor division, in the most conservative case is one unit on a decade scale with 10 units. Over six decades, this corresponds to l/60 span or less thari 2% of span. For conservatism, the calibration accuracy is assumed to be 5% of setting, by engineering judgement.

. 6.1.8 M&TE Error Effect

As stated in the Methodology Section 4.5, the M&TE error effect is conservatively estimated as equal to the reference accuracy of the device being calibrated. In addition, a common guideline is for M&TE equipment to be more accurate than the device being calibrated by a factor of 4: 1. Per Attachment B, the vendor specified reference accuracy of ±3 6% of input radiation (setting) for the system include extreme conditions and effects of LOCA (See Section 6.1.5). Because calibration of the device is performed during normal conditions, it is assumed that the M&TE equipment used to calibrate the meter has an accuracy equal Yt ofthe reference accuracy, ±36% · of the setting. Therefore, it is considered that the M&TE error of ±9% of tire reading for the meter is conservative.

6.2 LIMITATIONS

The anticipated post-accident operation duration is 4 months per the SCEW Sheets (Ref. 33.1).

7. CALCULATION

7.1 PROCESS MEASUR.EMENT EFFECT (PMEB) AND IR UNCERTAINTIES

7.1. l Process Measurement Effects (PMEb)

Per assumption 6.1.6, PM effect is included in the vendor accuracy term. Therefore,

PMEb=O

7.1.2 IR Effects (IRb)

Per assumption 6.1.4~ Insuiation Resistance Error is included in the vendor specification for the reference accura~y;. Therefore,

· IR~ = 0% signal IRbA =NIA


Calculation No. l-2-UNC-421 CALCI. Revision:O

7.2 SENSOR (RADIATION DETECTOR) UNCERTAINTIES

TAGNUI\.-IBERS:

MANUFACTURER: MODELN('.).:

1-VRA-1310, l-VRA-1410 -2-VRA-2310, 2-VRA-2410

. · Victoreen 877-1

(2.1]

(2.3] (2.3]

Based on Section 2.6, all uncertainties associated with the detector are considered in the Monitor accuracy.

7.3 INDICATOR (READOUT MODULE) UNCERTAINTIES

TAG NUMBERS:

MANUFACTURER: MODEL NO.:

1-VRA-1310-CRI, 1-VRA-1410-CRI [2.1] 2-VRA-23 I 0-CRI, 2-VRA-2410-CRI Victoreen [2.3] 876A• I [2.3]

The Indicator is designated as Radiation Readout Monitor/Meter. This device provides for Meter and Alarm outputs ..

7.3. I The following uncertainties are associated with the Meter output

Indicator Calibration Accuracy (ICA)

ICAM = ±36% setting [2.7.l]

Indicator Measurement and Test Equipment Effect (IMTE)

IMTEM = ±9% setting [2.7 .. 2]

Indicator Drift Effect (IDR)

ID~ · ·= ±36% setting· . [2.7.3]

Indicator Temperature Effect (ITE)

ITEM = ± 0% setting· [2 .. 7.4]

-Indicator Resolution Effect (IRES)

IRE-SM = ± l 0% setting [2.7 .. 7]

The total uncertainties associated with the Meter (IuM) can now be detennined as:

IuM .. = ± [(!CAM+ IM'ffiM)2 + IDRr.l + ITEi+ IRESM2]112 . ·

IuM = ± [ (36% setting -i- 9% setting)2"+ (36% setting)2 + (10 % setting)2]

112

IuM · = ± 58.50% setting

Project No. I 0597-112

Calculation No. l-2-UNC-421 CALCl · Revision:O

7.3.2 The following uncertainties are associated with the Alann output.

Alarm Calibration Accuracy (ICA) ...

· ICAA. =± 5% setting [2.7.l]

Alarm Measurement and Test Equipment Effect (IMTE)

IMTEA = ±3% setting [2.7.2]

Alarm Drift Effect (IDR)

IDRA = ±3% setting [2.7.3]

Alarm Temperature Effect (ITE)

ITEA = ± 0% setting [2.7.4]

Alarm Resolution Effect (IRES)

IRESA =N/A (2.7.7]

The total uncertainties associated with the Alarm (IuA) can now be determined as:

IuA = ± [ (ICAA + IMTEA)2 + IDRlJ112

IuA = ± [ (5% setting+ 3% setting)2 + (3% setting)2]112

IuA = ± 8.54% setting

No distinction is made between normal and accident for the indicator and alarm because per the design inputs in Section 2. 7, there are no additional accident effects for the indicator and alarm.

7.4 TOTAL INDICATION OUTPUT ERRORS

The total indication output errors are calc~lated by combining the uncertainties.forall-ufthe components in the loop that effeet the indication bas~d on the loop configuration (Section 2.1) and the uncertainties determined in Sections 7.1 through 7.3.

Meters . .. . . . . . . . The total output errors. (l<>M) for the indicators listed in Section 7. l are:

l<>M == ± ~fop;/] 112

IOM = ± 58.50% setting

Using the assumed value of 200R/hr from the EOP footnote, the total loop uncertainty, in terms of indicated unit. is as follows:

TLUM= IOM = ±(58.50% setting) x (200 R/hr)/100% TLUM= ±(0.5850) x 200 R/hr= ±117 R/hr

Project No. 10597_-112

Calculation No: l-2-UNC-421 CALGl Revision:O Page21

Therefore, the value of 200 R/hr (Ref. 3 .6.1) could have an indicated radiation level ranging from 83 R/hr (200 R/hr- 117 R/hr) td 317 R/hr (200 R/hr + 117 R/hr).

A!mm . The total· output errors (loA) for the High Range ContainmentMonitor System Alann under EOP accident conditions include the uncertainties of the radiation monitor meter, because during calibration the alarm is set to match meter indication (Refs. 3 .2.4 thru 3.2. 7). Therefore,

IoA = ± [(Iui)+(IuA2)]

1f2

IoA = ± ((58.50% setting}2 + (8.54% setting) 2] lf2

IoA =± 59.12% of setting

Per Reference 3.6.1 the alann should be set such that the containment radiation level would not exceed 10 R/hr at the detector. Therefore, since the allowable limit AL = 10 R/hr and total loop uncertainty TLU A = loAA = ±59.12% of the setting, the limiting setpoint SP, per Reference 3 .1.2, (Equ. 13-2), can be found as follows:

SP = AL - TLU A of setting. - M.

However, because the error of this device is calculated as a percent of the setting, which is a nonlinear function, and margin M = 0, smce all uncertainties have been accounted for, the above equation can be interpreted as follows: ·

AL= SP+ TLUAx (SP)

'.

The limiting Setpoint for the alarm can be then derived from the above equation as follows: .

AL= SPx(l + TLUA)

SP= AL 1+TLUA

SP= 10Rlhr 1+0.5912

SP = 6.3 R/hr .

As cakiilateci above, the alarm should be set to actuate.at the indicated valueof :s;; 6.3 R/hr as. shown on the radiation monitor meter. ·This .will ensilre that the alanri actuates when the. radiation level is :s;; 10 R/hr at the detector, as required· by Reference 3 .6. L

In addition, . based on the total output errors signal fo~ the met~r (TLUM = IoNM = ±58.50% of setting), the meter reading should be no more than 6.3 Rlhr, as confinned below:

SP:.· AL. 1+TLUM

SP= 1DR/hr 1+0.5850

Project No. 10597-112'

i

I i i l !

! !

Calculation No. l-2-UNC-421 CALCI Revision:O

SP=6.3 R/hr

8. CONCI..U.SIONS

8.1 RESULTS

The results listed below are acceptable for use with the assumptions and limitations listed in Sections 6.1, 6.2 and 8.2.

Meter The total indication loop uncertainty for the High Range Containment Monitor System Meters: 1-VRA-1310, "i-VRA-1410, 2-VRA-2310, 2-VRA-2410, at200R/hr(Reference3;(;J). is:

Accident: ±117 R/hr

Based on the above, the value of 200 R/hr (Ref. 3 .6.1) could have an indicated radiation level ranging from 83 R/hr to 317 R/hr (See Section 7.4).

Per Section 7 .4 the alann setpoint iS:

Accident:= 6.3 R/hr

Based on the above, the alarm should be set to actuate at an indicated value of~ 6.3 R/hr as shown on the radiation monitor meter. This will ensure that the alarm setpoint wUl not exceed the Technical Specification value of~ I 0 ·R/hr at the detector, as required by Reference 3 .6.1.

Per Section 7.4, the meter reading shall not be set more than 6.3 R/hr.

8.2 ASSUMPTIONS AND LIMlTATIONS

This calculation includes the followirigAssumptions and Limitations: . . .

The errors dete~ined in this calculation are analyzed_ for 4 ~onths post accident conditions.

Additional Assumptio~s are listed in Secti~n 6. ·

8.3 UNVERIFIED ASSUMPTIONS

There are no unverified assumptions in this calculation .... . . .


Calculation No. l-2-UNC-421 CALCl Revision:O FINAL

9. RECOMMENDATIONS

9.1 ECP 1-2-00-14

References in ECP 1-2-00-14 to Containment High Radiation Monitoring System uncertainty as indicated on monitors VRA-1310/1410 and VRA-2310/2410 should reference the uncertainties provided in this calculation.

9.2 ECP 1-2-V2-0l CALC 1

ECP l-2-V2-01 CALCl should be revised to note that errors associated with EOP indication and alann of the subject instruments listed in Section 1.0 are now included in this calculation.

Per ECP 1-2-00-14 (Ref. 3.6.1), 'the existing alarm setpoint is 6 R/hr. This calculation determined a setpoint of 6.3 R/hr. Therefore, the existing alarm setpoint is conservative, and no revisions are required to procedures as a result of this.calculation.

10.0 ATTACHMENTS

A. Walkdown Information.· B. Victoreen Containment Monitor Qualification Test J>Ian, Test Report 950.301, Addendum I,

Section IV. C. Information Management System (IMS) Recurring Maintenance Planning for l-VRA-1310,

l-VRA-1410, 2-VRA-2310 and 2-VRA-2410, viewed on 7/15/99.

1. Calculation Impact Assessment 2. Review Comment Form

Proje~t No. 10597-112

C/ . -

WALKDOWN PERFORMED FOR THE FOLLOWING INDICATORS.

Equip No. Manuf. Model No. Scale· Minor Div. .. ·.

l-QR-ll0-3 WAVcTt=K o u.; , ,. ~t... ,~o5sf!!.•es (?B&W?) P-~r r<Tt::> Of!.. ,,P-SP...T r.la M u1.-T'1PLY ev 10 r:;til ~~lo-LUI$

2-QR-110-3 II ,,

' (?B&W?) II

l-VRA-1310-CRI VU! "f"O R.e;(;"t•.J -· - SSE 1Jt>1E.1 l-VRA-1410-CRI - -2-VRA-2310-CRI - -2-VRA-2410-CRI --1-00AB-WM-REM ~~1-...... tg~~ - . 0-.46&'0 k.w /DO

1-DGCD-WM-REM l.oil2.S ll.B?o20 2-DGAB-WM-REM -2-DGCD-WM-REM -

.

*The Weschler catalogs for indicator model numbers VX-252 and HX-252 were compared to the front and rear of the indicators •. Based on similarity, it is assumed that the indicators listed above are W cschler · Model VX-252s. .

**The Weschler caiatogs for indfoa~r model numbers VX-252 and mC-252were ~mpared to the front and rear of the indicators. Based on similarity, it is assunied that the indicators listed above ate Weschler Model HX-252s. ·· · · · ·

PRnrr!SIGNfir$.~STP.DV~~D~. ·~taf..lt . DATE 7-9-11

PRDWSIGN(;..C/-18SOT/.,/t~ ~ DATE 7-'7- 9.'f

t

lt.11/ :

I

Calculation No.: l-2-UNC-421 CALCI RevisionNo.:· 0 Project No.: 10597-112 Attachment A Page Al

::ff·/

W ALKDOWN PERFORMED FOR THE FOLLOWING INDICATORS

Equip No. Manuf. Model No. Sea.le Minor Div.

fl•IFI· &10-Cll 1,.. VJ Vv - 2..62.. o- 400 taP/-i 2.. • t Ft• Sf ().llf: A_f;(J .. b /X) .. !l.o ''PP! 1- r ~l:- ~10-f.l.t l#~!J- s; w II u 1-TFil"'~fO~ apo. I ~DO II I<

I ()()() - I 9. ~() ,, ., 12 ()0. J4.()0 " ti

IA-DO• 1600 • If

I ,Sr; E PA G-~S 'I ~ J~ 1~-vM-2'10..dflJ; .. l/lt."'r()ocr-. 1 ,,.,.;,t> SCA ilf f .. vR.A-2410-~l?J !t--~-Jt t...• .8'-715 ' .. v 12.A. .. , ,, 0-UI l"h..t .4 .. ,_ - 8 .. 10~ l·Vf.1' - .t4t0-4eJ 1oc_2.-L-c.- ~ • \Dei

-•d'- ~-"'"·"- &- to«r_ ~- , .. .,,. - (, .. 1,.· '"':.

tri!&-4-·'-· ~- ID" lfr-~ -4- ... f,- ~- 10-1

/!? t' TT~ m .c: C ~ ')_ ,e· ...

(i...fl s=.t-41 O)'J' .E ,,. w \t1' - '2. ~z- 0 - ~ -_ ... ,,. __ -.. ~ ._ .. ,_. No~r t-d.'PX-"' £4 ?.ea I:> - ~ ... 1\10 JI J;

·-~~- ~ .. 1~ .. e£J: F\Dli - l()t)() • t~6' ~PM ·1-~-J. !.!I ,_~. ~- ' -- JC MJb W . .... . . ~j ~Ml\ .... ~·~ () • IM - If

·~M fJ -Ii! F..Mt) " L'1i'1 " ~ l tJ..! '° -!$~ " ·~ "I" ;&(»... ~ ()/)/) &f l·DO. ''

..

· 'The \lJesslder satal9gs fQr iadkater m9del ~bers VX 2S~ ~d HX JjJ v1~re sompar-ed to the fr-ont andr.car gfdie indkatgi;i:. Based OR similar.i~t. it is assumed tbjit tbe ii:idicators listed abg"e·are Wcschler ~~~· -~ . . . 0 PRIN~/SIGN G. c. AMoTTfil c ~ztg nATE ./ - L - 1' '?

PRIITT/SIGli /j;g,~~I.~ f(4pk~ . DATE ·:J-- 9- ' '

Calculation No.: I-2-UNC-421 CALCI Revision No.: 0 Project No.: 10597-112 Attachment A Page A2

./!. A J:> l A II 0 iJ MON• 1D RJ JJ6 / a r- /o

1-VRA- I 3 lo /t -VRA- 1410 ,/~- 'lf!.A-T?:JIO /t-Vf?A -1410 • ---~---tU!t"'-'"''-'-'--'{,.~£_,' - -···-··· . ····· .... ·. ··-···-··- -··------ . -----·-------

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---··-·-

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Calculation No.: 1-2-UNC-421 CALC1 Revision No.: 0 Project No.: 10597-112 Attachment A PageA3

Page'l v. :

"'

(")

~ C 452S JPG ------g '/A:\MV - . ---.:--------~-------~---~---'----"~-

7123199

--··--:--~---~---~-~--------

e iteadoU:t:8Mdde1:'f.!876-;,;.'1·4'!s a rack D:>unted loqaritlmic mic:roammeter that covers &ix dec:&d·

f radiation intensity. It utili:es int~ated circuits, printed circuit b::>Uds, relays

( other ccmmon electronic ca:iponents. It provides the hiCJh wltage required as the

d 11ecdon vol taCJe for the an-1· detect.or. A number of a.la:m functions and relay output. :c e ..... el . ..

b · · 11 provided •. A recorcer and computer output is also provided. 'l'he:.rudout is desiqned

.e qua11ffi"" . · · · · · · · · 'l:o meunt .. in a rack chassis &Dd this is no.rmally mounted in the- control rccm. The ALERT

:age to CU!IJ , . · · _5102

• Ea·~ani and the Electronic Check Source vill be wired for automatic reset and operation

to a Billtspec:Uvely. 'l'he Hiqh Alam will be wired fer unWll reset. The power transformer of

b, : e 876-l Readout is of the dual primary type to accamoc!ate. either a ncminal 120 VAC or assem .y

.g shall 1

2o VAC power input. The primaries· are to be vi.red in parallel for 120 VAC and in serie!

if,~or 220 VAC. For this qualification testing, the primaries shall be vired for 120 VAC. :g spec ·

Critical Per!or=ance Characteristics .surance ._

1 f acteris~ic Minimum Nominal : on o a~ ----= v1dual ~. Ranqe 101 N/A

Units/ltema.rks

ccion c::t· Input Curren~ 6.S to 7.Sxlo-i C 6. S .to 7 .SxlO-i. A . • Record~r Out~ut 0 N/A +5 de volts, lo9arit:lm:ic

• Computer Out?ut 0 N/A +5 de volts, loqaritlu:ic

System Accuracy. No limi't N/A :!:36 \ of input radiation

·Ae:umulative@ meter

• System Accuracy; No limit H/A :!:28 ' of input radiation

( Analoc; Outputs

Pover Requirements a) ac voltaqe 108 120 132 VAC PJ!S @ 60 :!:j &%. b) Battery Paver 22 28 32 voe @ 600 m. ADC max.

• Pcver Sut'Ply.eoeff. N/A H/A :!;0,17 ' change/.,,,lt acl.included in ll/°C E: • F above

'l'empenture Coe.ff. a) N/A N/A :,40

.50, Appe-.

) I .301

! 10

.

~ NC. . .a.a .. ,., \Ill

c-- l ·~ .an· - -0 . NO.i2.

· 907fv. LET.

i

b) H/A N/A ±,25 I/hr/CC . .

These are ci=ul.ative errcrs ca1c:ul.ated usinq the Sum of the ·deviatiens of t.'ie component errors ass0ciated with the d.etectcr,. &mplifier and meter (vhere applicable). Component errors include utreme. tempera cure and humic!i t'/ effec .. s. e"xuei:l voltaqe variation effects, radiation am the:mal a9in9 (where applicable)•. pemanent vibration or seiSmic ef!ects and u:X:A·£nvironment effects on awlical::J.e portions of: .'the system.

Calculation No.: I-2-UNC-421 CALCI ·. Revision No.: 0 Project No.:. I0.597-112 Attachments Page BI

1129n9 DATE ISSUED CHANGE NOTICE HUMBER

· . Tes'e REport 950. )Ol Addendum I Section VI t>a9e ll

'

"VICTOREEN, INC. A ~..cioo. Co<ooricoa'o s..os.o.a..,

Ccntainmen,t Monitor

L.cTC•HN! Quali~ication Test Plan

PG.. s OF 23· DWG. NO •

D~TE 7/27/28 907384

(

-critic1

~.1.1 Critical Performance Characteristics (continued) t!jllper. ( Characteristic: Minimum Nominal Maximum Uni ts/Remarks temper.

.J. Electronic Check Source ttelati·

Cf cl~ 'time . 6.S 1.s 8.S seconds Jtelati•

!Simulated level 9.0x102 . lx103 1.lxl03 1/hr trradi • ;,

?Automatic period p 23 2S.6 28 minutes K:lunti • • ~- Alarm Level Indication Range

&/hr cheok sourc~ lack C

. SAFE lx102 lxl03 l.lx10J supp or

*AI.ERT lx101 N/A 1xl07 R/hr I Analog I

*HIGH lxl01 N/A lxl07 R/hr volt o I .1 Critic::

L. ·Alarm Relay Actuation hnge I 'SAF£ lx102 lxl03 l.lx103 R/h"F check

Input source::

*AL!RT lx1ol ix107 R/hr QutiJUt

N/A ' '*liIGH lx1ol _. lxl07 R/hr

Input K/A

Ac::cun M. Alarm Level Accuracy Power

ALERT No l 1mi t ·l 3 % of setting Line•,

HIGH No limit l 3 % of setd.ng Ambie1 . .2 Crit11 •NOTE - Set points are continuously adjustable throughout the range. Tempe:

Calculation No.:· I-2~UNC-421 CALCI Revision No.: O Project No.: 10597-112 Attachment B Page 82

Test Repor~ 950."301 · Addenchml I Seetion·VI ~aqe 12

VICTOREEN, INC • .. $Plelle•·Glo0e Coroo•- s..os-a•··

. •. Containment Monitor

Tempe·

Relat

In ad

Moun~

Qualification Test Plan ------------.---------+~:.::.=:..::=:.:;:::~T:::;;G;-;;;N0:;-1" 2 ·.

PG.. 6 OF Z3 r:M 907J84~-'I. LET.

REV. LET. . DA TE ISSUED CHANGE NOTICE NUMBER DATE 7/27/78

i l I

r I

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I ' I I i '

I I I I

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·-•

.. .. ,, (

;k

:1

:k

:ing

:ing .·· (

Critical Environmental Parameters

Characteristic JHn:brum

Temperature (1tora1e) 32

Temperature (operating) 40

ttelative Humidity (storage) 0

le~ative Humidity (operating) 10 .,

Irndiation 3.S

Nominal Ma:Ximum

'H/A 150 80 120

N/A 95

so 90

10- lxl03

Units/Remarks OF

. OF

% (non -condensing)

% (non-condensing) ~d @ &oco.:·inteqrated ever

it • 40 years life. Mciuntinq !bun~ed in half of rac:k chassis

• laclr.··Oassis.-.(Part ;No. 876-1-~5) 4110unted by front tabs in cabinet that provides

support for rear of rack chassis.

~l.~J.Wlk~~B~~·tor,.Mode~·B79-1~1 A module that isolates and converts the O to S

volt output of the Readout to the 4 to 20 ma input of the recorder.

Critical Perfonnanc~ Characteristics

Input Signal Range 0 N/A s.o Output Signal Range 4 N/A 20

Input Illlpedance 100 . N/A No limit Acc:urac:y Ho limit N/A 1

Power Requirements 108 120 . 132

Line Voltage Effect Ko limit N/A 0.1

Amb~ent Temp. Eff~ct Bo limit N/A .01

Critical Environmental Parameters

Temperature (storage) 32 N/A 150

Temperatur~ (operating) 40 80 UO.

lelative Hu:iidity ·10 50 90 Irradiation 3.5 10 ix103

Ko'lm~ing

.. Calculation No.: l-2-UNC-421 CALCl ·· Revision No.: . 0

Project No.: 10597-112 . Attachment B

Page B3 (Final)

l/29/79

DATE IS:SUED OfANGE NOTICE NUMBER·

VDC

mA.dc

c a ' % of cakulaud output from

1 · npu

VAC RMS. 60 :3, SO\'.\ max.

% of F.S./10% line change

% of F~S./°C

°F °F % (non-condensing)

Rad @ 6 Cto inteqra ted over 40 years lif;e.

~tee! in half of rack 1ri.th mau.-itinq brackets •

Test Report. 959.Jal Addendum t Section VI Paq~ 13

VICTOREEN, INC. A sr.e-•Clooe c:or-- Suoll4•'Y

Cont:ainm.ent Monitor Qualification Tes; Plan

PG. 7 OF . 23 DWG. NO. 9073.84

DA TE 1 /27 /78

chassis

12-V2-0l: J•VRA-1310

Job Order Nbr : R0004694 #of Act: _3 Prim JOA:_ Unit/System : 1_ RMS_ Recur Task Nbr: 00004295 J/O Type: LIB_ J/O Status/Date: PLNNED 07/14/92 J/Q Pri/Ct4 · : 37 _ N/R Maint. Cat: R3 Plan Code : NDO Last Update : 02/22199 J/O· Description: PERFORM '* 1 IHJ,>6030.IMP.3l1.. ________ _ AIR Nbr : A0016417 Resp Org: MTI_ . Outage Class : 9_ Assigned Pliir · : MTI NetWr~:· Est Duration : _ 2 · Equip Code :.F . . . .Trairi: _ Est St8rt Date: __ _ FEG . : 113.13__ SafetY Rel: YES . . ~st Comp Date : __ _ Comp Nbr. Disp FEG: 113.13 __ EQ: Y ASME Class: N

. Comp I FEG Desc: ERS-1300 (LOWER CONTAINMENT RADIATION MONITOR) __

Unit Location : _ Bldg:_ Elevation:_ Room No:: __ Type: __ Equip Reqd Modes: I 2 3 4 _ ~ _ Work Modes: 5 6 ____ _ Pre Maint Test Reqd: N (YIN) Post Maint Test Reqd: Y (YIN)

. Sched Type: I INTERVAL - NEXT DUE BASED ON LAST PERFORM DAT PM Type: PETC Tech Spec' Freq/Unit: _72 W Next Reqd Date: 10/01/99 Drop Dead Date: 02/04/00 Plant Freq/Unit . _72 W Next Plant Date: 10/01/99

· Tech Spec Cale Meth: A Last Perfonned Dates: 05/15/98 12/27/96 07/13/95 Special Sort Code 1: N'I'S _ 2: __ 3: _. _ 4: 5:

CMMDS: AR,COMP,NEXT,R,CREM,ACT,A##,PRINT,PRINT##,INQ,PSHEET, WRKPK

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,.., g. g !a: E. \J"' - 0 "' ..... ~ z ::s ::?.

::s 0 zo -.:. 0 ::s (j - :. z

0 0 VI 0.:. \0 .....i ' ·N

·---~---~--------·-------·-··---·---·---~~-~-~~-----~~-·~·----·--~---·--··----....,..··--·-·-- --··- ......... -. ~··-- ,._. __ -··--··-

12-V2-0l: l-VRA-1410

Job OrderNbr : R0004~96 #of Act: _3 Prim JOA:_ Unit/System: l_ RMS_ Recur Task Nbr: 00004297 J/O Type: LIB_ . J/O Status/Date: PLNNED 07/16/92 J/O Pri/Ctd · : 37.:_ N/R Maint. Cat: R3 Plan Code : NOO Last Update : 02/22/99 110 Description: PERFORM •• 1 IHP6030.IMP.312 .. _. ______ _ AIR Nbr . : AOOl6419 . Resp Org: MTI_ Outage Class : 9_ Assigned Plnr. : MTI Netwrk: Est Duration : _2 Equip Code · . : F . · . Train: .· Est Start Date: __ _ FEG : J 13.14_·_. _· · Safety Rel: YES· .. Est Comp Date : __ _ Comp Nbr . . . Disp FEG: 113.14 __ EQ: Y ASME Class: N Comp I FEG Desc: LOWER ~ONTA.INMENT RADIATION MONITOR ______ _

Unit Location··=_ Bldg:_ El.evation: _. _Room No.: __ Type: __ · Equip Reqd Modes: I 2 3 4 ..:_ __ . . Work Modes: 5 6 ____ _ Pre Maint Test Reqd: N (YIN) . Post Maint Test Reqd: Y (YIN) Sched Type: C CALENDAR..: NEXT DUE DA TE CALCULATED BASED UPO PM Type: PETC Tecli Spec Freq/Unit: _72W Next Reqd Date: 08'23/99 Drop Dead Date: 12/27/99 Plant Freq/Unit : _72 W Next Plant Date:· 08/23/99 '.fech Spec Cale Meth: A· Last Performed Dates: 04/06/98 11/26/96 06129195 Special Sort Code 1: NTS_ 2:,_:_· .3: _. _. _ 4: 5:

CMMDS: AR,COMP,NEXT,R,CREM,ACT,A##,PRINT,PRlNT##,INQ,PSHEET, WRKPK

12-V2-0l: 2-VRA-2310

Job Order Nbr : R0038471 #of Act: _J Prim JOA:_ Unit/System: 2_ RMS_ ·Recur Task Nbr: 00017627 J/O Type: LIB_ J/O Status/Date: PLNNED 04/12/96 J/O Pri/Ctd ·. : 37 _ NIR Maint. Cat: R3 Plan Code : NOI LQSt Update : 04/25/99 J/O Description:PERF.**2IHP6030.IMP.41 l (CNTMT HI RNG VRA-2310)._ AIR Nbr : A0084097 .· Resp Ol'g: MTI_: Outage Class : 9_ Assigned Plrir : MTI · Netwrk: Est Duration : _l Equip Code · : F . Train:· Est Start Date: __ _ FEG :213.00 __ •Safety Rel: YES EstCompDate: __ _ CompNbr .. DispFEG:213.13 __ EQ:YASMEClass:N

. Comp I FEG Desc: N'.I. AND RAD MONITORING (NUq.EAR INSTRUMENTATION)_

Unit Location : ~ Bldg:_ Elevation:·- Room No.: __ Type: __ Equip ReqdModes:l 23 4 5 __ Work Modes: 7 ------

. Pre Maint Test Reqd: Y (YIN) Post Maint Test'Reqd: Y (YIN) .. Sched Type: C CALENDAR - NEXT DUE DATE CALCULATED BASED UPO PM Type: PETC Tech Spec Freq/Unit: _72 W Next Reqd Date: 06/07/99 Drop Dead Date: 06/07/99 Plant Freq/Unit : _72 W Next Plant Date: 06/07/99 Tecfl Spec Cale Meth: B Last Performed Dates: .o 1/19/98 05129196 __ _ Special Sort Code 1: NTS_ . 2: RCM_ · 3: __ 4: 5:

CMMDS: AR,COMP,NEXT,R,CREM,ACT,A##,PRINT,PRlNT##,lNQ,PSHEET, WRKPK

-N

~ .n b -

--------·------------····---------------

I

12-V2-0l : 2-VRA-2410

Job Order Nbr : R0057597_ #of Act: _3 Prim JOA:_ Unit/System: 2_RMS_ Recur Task Nbr: 000176281/0 Type: LIB_ 110 Status/D_ate: PLNNED 03/24/96 110 Pri/Ctd : 37 :_ N/R Maint. Cat: R3 Plan Code : NOi Last Update : 03/08/99 110 Description: PERFORM .. 2IHP6030.IMP.412 •. ________ _ AIR Nbr. .: A0084098 · Resp Org: MTI_ . ·Outage Class : 9_ Assigned Plnr : MTI Netwrk: · . . Est Duration : _I Equip Code .. : F . Train: _ ·Est Start Date: __ _ FEG : 213.00__ Safety Rel: YES · Es_t Comp Date: ---Comp Nbr. Disp FEG: 213.14 __ EQ: Y A~ME Class: N Comp I FEG Desc: N.I. AND RAD MONITORING (NUCLEAR INSTRUMENTATION)_

Unit Location · : _ Bldg:_ Elevation:_. ·-Room No.: __ Type: __ Equip Reqd Modes: 7 ~----- . Work Modes: 7 ------ · Pre Maint Test Reqd: N (YIN) Post Maint Test Reqd: Y (YIN) Sched Type: C CALENDAR- NEXT DUE DATE CALCULATED BASED UPO PM Type: PETC Tech Spec Freq/Unit: ~72 W Next Reqd Date: 04/24/00 Drop Dead Date: 08127/00 Plant Freq/Unit : __ 72 W Next Plant Date: 04/24/00 Tech Spec Cale Meth: A Last Perfonned Dates: 12/06/98 07124/97 05/22/96 Special Sort Code ll NTS_ 2: RCM_ 3: __ 4: 5:

CMMDS: _AR,COMP,NEXT,R,CREM,ACT,A#l#,PRINT,PRINT##,INQ,PSHEET, WRKPK .

()

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-~-~--~---------- .. ··~---------~-------·--·--·--·--·

I

----··----~---- ----- -~-· ------·-·---~- ...... -. - -~--

---------------~--~~~

Calculation Impact Assessment

PARTl

Calculation No. I-2-UNC-421 CALC'.:l

Attachment I Calculation No. I-2-UNC-421 CALCI

Rev. No . ..JL Page I of ~

Rev. 0.

Title: Post-Accident High Range Containment Area Radiation Monitoring

Interdiscipline Coordination Required? 181 Yes 0No

If NO, Explain:

Initial/Date Initial/Date 0 Mechanical 0 N~clear Safety

Engineering Analysis. 0 Electrical/l&C O Nuclear

Engineering Licensing 0 Structural -@=l faintwenee- A/M $1. 11>f,j9r_ Engineering 0 System 0 Chemistry Engineering 0 Production ~ R:et4ietien PM Jb i&1/'l/fr Engineering · . -Pf.gte6tien-

* .,f

0 Programs ~ Op_ei:atiaas- /I/IA )}Id Nj_'1/1?

.,;. Engirieering

0 Other 0 Training

I l I

j I j

! f

I i

I I

I I I I

I

Calculation Impact Assessment

PART2

Attachment l Calculation No. l-2-UNC-421 CALCl

Rev. No . .Jl Page2of ~

List sections and/or paragraphs reviewed. List applicable calculation attributes identified in each document. List Condition Report number(s) initiated as a result of this review.

TECH SPEC SECTIONS REVIEWED/IMP ACT: Section 3/4.3.3.l and Table 3.3-6 & Bases, -After review of the Tech S~ecs and applicable Bases, there is no impact to plant Tech Specs as a result of the instrument uncertainties established in this calculation.

Section 4.0.2 and Bases - This section provides infonnation and bases for calibration time interval extension for this calculation.

UFSAR SECTIONS REVIEWED/IMPACT: UFSAR Chapters 7 .5, · 7 ,8~ 11.J and. Table 7 .8-1. The UFSAil was revi~wed and no impacts were identified. The UFSAR does not specifically address methodologies for detennining uncertainties. This calculation does not impact the current UFSARnor does it require a change to the existing plant configuration.

SER SECTIONS REVIEWED/IMPACT: After a review of the SER and applicable supplements, there were no impacts identified as a result of this calculation. The calculation only establishes the uncertainties associated with the Post-Accident High Range Containment Radiation Monitoring instrumentation. The existing licensing basis and regulatory position is unchanged.

DESIGN BASIS DOCUMENTS REVIEWED/IMPACT: DB-12-RMS, Section 2.1.2.1 and 3.5 -After a review of the DBD, there were no impacts identified as a result of this calculation.

PROCEDURES REVIEWED/IMPACT: . . ... 1IHP6030.IMP.311, Rev.3, UHP6030.IMP.312, Rev. 3, 2IHP6030.IMP.41l, Rev. 3 and

· 2IHP6030JMP .412; Rev. 3. These procedures provide calibration inforination for the Radiation Detector and Radiation Readout Module for the calculation. - · · · ·

. . . . .

Th~ following procedures could be imp~cted as· a result of this in~trument uncertainty ~alculation. 1-0HP 4030.STP.O?O, 1-~ 4030.STP.095, 2-0HP4030.STP.030, 2-IHP.STPJ~5

DESIGN/LICENSING PROGRAMS REVIWED/IMP ACT:· NIA

OTHER CALCULATIONS REVIEWED/IMPACT: · ECP l-2-00-14 ;_References to Containment High Radiation Monitoring System uncertainties as

indicated on monitors VRA-1310/1410 and VRA-2310/2410 should reference the uncertainties provided in this calculation (1~2~UNC-421 CALCl}.

~ I

. t t I

l l I i

Calculation Impact Assessment Attachment 1 Calculation No. l-2-UNC-421 CALCI

Rev.No.JL Page 3 of :3

ECP 1-2-V2-0l, Rev. 4-Should be revised to note that errors associated wi#l EOP indication and alarm · sefpoint of in~ruments listed in Section I are now included in calculation 1-2-UNC-42 .I CALC I.

' . . . OTIIER DOCUMENTS.REVIEWED/IMPACT (e.g., Administrative Tech Specs, Fire Hazards Analysis,

Safe Shutdown System Analysis): None

PART3 (Identify all files that were searched and the search criteria used)

FOLIO files searched and search parameters used: 1-UFSAR 2-SER 3-DBD

Search Parameters: Radiation Monitoring System High Range Radiation Monitoring

•

Cale. No: l-2-UNC-421. Calcl. - Rev.0 ~

Attachment __fl i:>jtJ1/f f Page_l_of_3_

Review Comment Fom1 .

Calculation No.: l-2-UNC-421, Calcl I Revision: 0

Title · Post Accident High Range Containment Area Radiation Monitoring

Comment Attribute Comment Resolution # #

1 NIA Section 1.0, page 4 in, the second to the last paragraph .. In the first Incorporated sentence, "alarm" should also be included in the descriptions.

2 2b Section 2.2.2, under peak pressure, 29. I psia (Unit 2) was added. per Reference 3.3.l, Unit 1: 28.3 Both values, 28.3 and 29.l psia, are psia, Unit 2: 29.1. Justify the use of provided for info only. 28.3 instead of 29.1 psia in the table ..

3 2b, Section 2.4.1, Ref. 3.2.4,-indicate an . input span of 6.90x10·11 to 6.90x10·3,

output span lxl0° to lxl06 R/h. The Incorporated

value indicated in the table is does not match the procedure. Comment also applies to Section 2. 7. Last paragraph, second sentence, use .-

Tech Spec surveillance requirements instead of using IMS._

4 2a Section 2.6, indicate value. for input span, output span and an URL. Incorporated Section 2.4.1 indicated NA. Resolve

NIA the~e discrepancies. -· Last sentence, should state that its

·considered-in the monitor .. · 5 Ila Section·2.7.l through 2.7.7, clarify -Issue clarified. It is % of the setting,

the % value indicated (%span, % - as provided by the vendor. See setting,% input). Attachment B.

6 3b Section 3.2.2,.Reference specific section of Tech Spec.

3c Ad~ change # 3 after revision for . Incorporated · Sections 3.2.4, 3.2.5, 3.2.6 and change# 4 for Section 3.2.7.

7 - 3c Section 3.5.1 should be revision 4, -.. . .

Section 3.5.2 should be revision 2 Incorporated

Source: 12EHP 5040 DES.003, rev. l

I

I i l

j

I I t

8 NIA

9 NIA

10 6a

11 6b

12 NIA

13 7

14 7c

Cale. No: l-2-UNC-421. Cale 1. Rev.O

Attachment __J'l Page_2_of_3_

Review Gomment Form

Section 4·.1, Incorporate minor comment and define EOP normal Incorporated environment. Provided in separate mark.up. Section 5, indicated no acceptance criteria for the calculation. Section 1, Incorporated indicated that the purpose of the See Section 5. calculation is also to confmn the alarm setpoint that the Tech Spec shall not be exceeded. In section 6.2, add as a limitation: The errors determiiled in this Incorporated calculation are analyzed for 4 months. This is consistent with other tincertainty calculations. Section 6.1.8, provide basis to permit 5% of setting is based on Attachment verification of the 5% of signal. A information and is an engineering

judgment. Section 7 .2, Incorporate minor comment for the first sentence Incorporated provided in separate mark-up. Sections 7.3 and 7.4 Incorporate comments as provided in separate Incorporated mark-up.

Section 8.1, should be the resulfof the cB.lculation. Purpose of tlie · Incorporated calculation akeady discuss in Section . .. I. 'Do not sliow calculation in this · Section. Incorporate comments as . provided in separate mark up:

...

·CR P.;99-21489 has been.initiated to ...

track resolution of t4ese comments .

. .. . . . .

..

. Source: I2EHP 5040 DES.003, ~v. I

Cale. No: l-2-UNC-421, Calcl.

Review Comment Form

Reviewed by: . N.R. ~ir~ /~ :;f./&1~w Print/Sign

Source: l2EHP 5040 DES.003, rev. I

Rev.O Attachment--.£2. ;o/c7/rf

Page _3 _ of_3_ $/-

10/'f?lrr· Date

1-2-unc-421 calc1, rev. 0, 'post-accident high range … · 2017-06-29 · 1-2-unc-421 calc1...

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