ML16277A124

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ERS-SFL-88-027, Rev. 3, Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B.
ML16277A124
Person / Time
Site: Beaver Valley
Issue date: 08/10/2011
From: Lebda J T
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
ERS-SFL-88-027, Rev 3
Download: ML16277A124 (13)
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FORM 1/2-ADM-1611 F28 Rev 2 RTL#A9621A Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation

-Subject No. PAGE 1 OF Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101 A/B ERS-SFL-88-027 13 ' Reference HPP _EPP T/S CR DCP Category Unit 1 Unit 2 D Technical Position IX I Technical Evaluation D Calculation D [8] Purpose The purpose of this technical evaluation is to document the derivation of alarm setpoints for Unit 2 DRMS monitor 2CHS-RQ101A/B.

Alarm setpoints were previously documented by SWEC 12241-UR(B)-410, Rev. 1. Also provided are revised database engineering unit conversion factors. Also the monitor indication (without consideration for instrument error) associated with an RCS activity concentration of 21 uCi/g is calculated.

D ORIGINAL ISSUE IBJ REVISION#

3 Revision description:

This revision adds the letdown radiation monitor indications that correspond to an RCS concentration equivalent to 21 uCi/g dose equivalent iodine-131 (DE 1-131). This value is proposed for use as part of the NEI EAL (Emergency Action Level) upgrade project for EAL SU9. Updated references.

Updated the source term/basis to use 12241-UR(B)-484 data. " by ff.fI. //fl _ li'-10-11 independent review (calculation only) John . [eb 8 r --date Michael Untried <;<-1 "5 -z.o t I date NIA -Not a Calculation date ' Checklist Attachments 00 Purpose l&J Results 00 Data Sheets 00 Methodology

!&I References D Illustrations 00 Input Data D Printouts D Code Listings I&) Transmittal to BVRC D Supt, Rad Ops Author: John T. Lebda BV-ERF !&I Original RP ERF FILE D Supv, RP Services Hal Szklinski BV-SIM D MGR, Radiation Protection D Supv, Rad Waste/Effluents

!RI Michael Unfried SEB-3 D Beaver Valley Power Station Radiation Protection T Po 'ti on/

Subject:

Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B PURPOSE RE I No.: Page: ERS-SFL-88-027 2 The purpose of this calculation is to determine the alarm setpoints (alert and high) for the Unit 2 letdown radiation monitor, CHS-RQ101A/B high range and law* range channels.

This revision incorporates changes necessary to reflect implementation of Unit 2 Technical Specification Amendment 101 1* This Amendment lowers the reactor coolant system Technical Specification allowed activity limit which forms the basis for the monitor alarm setpoints.

Also the monitor indication (without consideration for instrument error) associated with an RCS activity concentration of 21 uCi/g is calculated.

DISCUSSION The basis for the CHS-101A/B alarm setpoints is discussed in the Unit 2 NRC SER section 4.2.4.2 2 which states "The reactor coolant letdown monitors -

which include high-and low-range offline liquid monitors in the reactor coolant letdown line that can detect conditions that indicate fuel rod failure ... ". Further the Unit 2 UFSAR 3 Section 4.2.3.3 states "Provisions for detection of fuel rod failure include high-and low-range off-line liquid monitors in the reactor coolant letdown line as discussed in Section 11.5.2.5.1 O". UFSAR 4 Section 11.5.2.5.10 provides a general description of monitor configuration and function, but does not mention the alarm setpoints.

These documents establish the licensing basis for the monitor and monitor alarm function.

Note that the extent of fuel failure or any other specifics regarding the alarm setpoints is not mentioned.

Calculation History: SWEC 12241 UR(B)-410-1 (1986)5 This calculation package initially provided high range monitor alarm safety limit values based on 1 % failed fuel (high setpoint) and the Technical Specification RCS concentration limits (alert setpoint), and low range monitor alarm safety limit values based on expected RCS activity (high setpoint) and 0.05% failed fuel RCS concentration

{alert setpoint).

Revision 1 was made after it was discovered that, although there are two monitors, they feed a common alarm channel. Therefore, only one each of a high and an alert setpoint are possible.

The revision 1 setpoints were based on the Technical Specification RCS concentration limits (48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> action limit of 1.0 µCi/g DEl-131) for the high setpoint, and the alert setpoint was set at 75% of this value. ERS-SFL-88-027-1 (1989)6 This calculation revised the monitor setpoints using updated monitor isotopic efficiencies.

The previous SWEC calculations were performed using preliminary vendor calibration data. This calculation maintained the setpoint bases established in 12241-UR(B)-410, Rev. 1 5. ERS-SFL-88-027-2 (1999)21 This revision was made to address source term changes resulting from Unit 2 Technical Specification Amendment 101 1. This Amendment lowers the Technical Specification reactor coolant system (RCS) activity concentration limit from 1.0 µCi/g dose equivalent iodine 131 (DEl-131) to 0.35 µCi/g. Additionally, the basis for defining DEl-131 is changed to use dose conversion factors based on ICRP 26/30 7*8 and taken from Federal Guidance Report 11 9* (These changes had been previously implemented at Unit 1 10.) Additionally, this calculation incorporates a recent update made to the design RCS activity concentrations 11*12*

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Ca

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Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B I I No.: Page: ERS-SFL-88-027 3 This information is used to derive the revised Technical Specification reactor coolant system (RCS) activity concentration limit for each radioisotope.

Also, this change has a significant impact on the calculated alarm setpoint and monitor conversion factor (CF11 ). The impacts are further discussed in the RESULTS section of this calculation package. ERS-SFL-88-027' Rev. 3 (2011) Added the letdown radiation monitor indications that correspond to an RCS concentration equivalent to 21 uCi/g dose equivalent iodine-131 (DE 1-131). This value is proposed for use as part of the NEI EAL upgrade project for EAL SU9. Updated references.

Updated the source term/basis to use 12241-UR(B)-484 19 data. Comparison to Unit 1: The Unit 1 letdown radiation monitors setpoints are based on an RCS activity concentration with 1 % failed fuel 13* The high-high alarm is set to actuate at an RCS concentration while operating with 1 % failed fuel and the high alarm is set to actuate at an RCS concentration while operating with 0.5% failed fuel. These concentrations are much higher than the Technical Specification activity concentration limits. The difference between the two Units is apparently due to the SWEC analyst's decision to select the Technical Specification activity concentration limits as the setpoint basis (rather than the originally used 1% failed fuel) when revision 1 of 12241-UR(B)-410 was performed.

Using this as the setpoint basis will cause the Unit 2 monitor to alarm with a lower amount of failed fuel as compared to that for Unit 1. Because of the difference discussed above, a different methodology must be used to determine the activity concentrations between the Units. At Unit 1, with the setpoint based on activity concentration with 1 % failed fuel, it was necessary to make adjustments in the source term to consider that additional RCS clean-up will occur when the letdown system is operated at a flow rate higher than 60 gpm, the value at which the design activity concentrations were calculated.

A higher flow rate, normally approximately 105 gpm, is routine and this is taken into consideration in the alarm setpoint calculation.

At Unit 2, using the Technical Specification activity concentration limit at the setpoint basis, any need to adjust for variation in activity removal is eliminated.

With regard to the proposed EAL monitor indication of 21 uCi/g, the only difference between Unit 1 (cpm) and Unit 2 (uCi/cc) is that the calculations are done to provide indication in the appropriate units. METHODOLOGY The methodology of this calculation is identical to that used in the previous revision.

This RCS isotopic mix is assumed to be that calculated for the Technical Specification concentration limit. These values are then multiplied by the monitor efficiency specific to each radioisotope and the resulting count rates are summed to produce the monitor response.

Because Technical Specification concentration is expressed in units of µCi/g and efficiency is expressed as cpm-cc/µCi this calculation corrects for density* at the monitor. Finally, because the isotopic mix is updated, the monitor engineering unit conversion factors (CF11) are recalculated.

All of the mathematical operations are provided in further detail on the Attachment 2 spreadsheets.

Beaver Valley Power Station alu ti I I *o

Subject:

No.: Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B ERS-SFL-88-027 4 Instrument error is considered when determining the alarm trip setpoint.

BVPS Unit 2 is committed to Regulatory Guide 1.105 14* This document provides the basis for instrument setpoints for safety related systems, and is implemented through Radiological Engineering Administrative Manual procedure BVBP-RP-0002

15. Therein, the Total Loop Uncertainty is defined as: TLU = (EA 2 + PA 2 + CA 2 + SA 2 + DA 2 + +LA 2 + TA)0*5 [eq. 1) And the Trip Setpoint as: TSP= AL I [1+(%TLU/100+(%DEADBAND)/100)

[eq. 2] The TLU has previously been determined to equal 21%16* Because this value is derived elsewhere, the reader is referred to the source, and BVBP-RP-0002, for explanation of the variables in the error analysis equation.

The TSP is: TSP = Activity cone CAL) (uCi/cc) = Activity cone (AL) (uCi/cc) [eq. 3) 1+(21%/100)

+ (10% / 100) 1.31 INPUT DATA AND ASSUMPTIONS

1. Reactor Coolant Technical Specification activity concentrations

[19, Table 9.2] 2. Basis for Technical Specification activity=

0.35 µCi/g DEl-131 [11 (48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit) 3. Proposed EAL monitor indication=

21 µCi/g DEl-131 [11 (Technical Specification instantaneous limit) 4. CHS-RQ-101A/B nuclide efficiencies

[17] (Nuclide efficiencies are listed in Attachments 1 & 2) 5. Fluid temperature at CHS-101A/B

= 130 °F [5] 6. Fluid density at CHS-101A/B

= 61.6 lbm/ft 3 [5] 7. Fluid density -Standard = 62.43 lbm/ft 3 [Calculated]

7.481 gal/ft 3

  • 3785.3 cm 3/gal
  • 1 g/cm 3 / 453.592 g/lbm [18) 8. Instrument Error= +/-21 % [16]

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation

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Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101AIB RESULTS 3 No.: ERS-SFL-88-027 5 For the high range monitor and the *low range monitor (Attachment 2), the monitor response in cpm is calculated using activity concentrations at the (48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) Technical Specification limits. Because the RCS activities are given in µCi/g, only a slight density correction is necessary to determine the concentration in µCi/cc at the monitor. Consistent with the current analysis of record (and with Unit 1 ), the monitor response*

is calculated in terms of gross activity.

That is, those isotopes that cause no monitor response are included.

By employing this method, the monitor reading will represent total activity, even though some isotopes cannot be detected.

Also, it is important to note that the monitor reading in µCi/cc represents the concentration at the monitor, and not in the RCS. Because of density differences, this difference is approximately 40%, with the actual concentration in the RCS being lower. The setpoint calculation is based on mass concentration rather than volume concentration, and is not affected by this fact. . I From Attachment 2: Note: The spreadsheet carries higher precision than shown below. Technical Specification activity concentration

= 4.97E+01 µCi/cc at the monitor. This is the analytical limit (AL), or process safety limit. Applying equation 3 to determine the high alarm trip set point (TSP): 4.11 E+01 µCi/cc = the high alarm trip setpoint with instrument error adjustment (4.97E+01

µCi/cc/ 1.31 ). This should be set with the background subtract feature active, or with the corresponding background added to the alarm setpoint.

and taking 75% of the high setpoint to calculated the alert alarm setpoint:

3.08E+01 uCi/cc =the alert alarm trip setpoint.

This should be set with the background subtract feature active, or with the corresponding background added to the alarm setpoint.

Note: Although there are two monitors (high range and low range) they both provide input to a single set of alarms (high alarm and alert alarm). The corresponding high range monitor response=

1.38E+03 cpm / 4.97E+01 µCi/cc The corresponding low range monitor response=

3.49E+05 cpm / 4.97E+01 11Ci/cc 3.60E-02 µCi/cc-cpm

=the high range monitor engineering unit conversion factor (CF11) (4.97E+01

µCi/cc/ 1.38E+03 cpm) 1.43E-04 uCl/cc-cpm

=the low range monitor engineering unit conversion factor (CF11) (4.97E+01

µCi/cc I 3.49E+05 cpm)

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation

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Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B RE I 3 No.: Page: ERS-SFL-88-027 6 As compared to the current alarm setpoints, the values calculated herein are slightly higher. This is attributed to use of the revised term used in this revision.

The influence of the revised source term was previously evaluated in 10080-UR(B)-508 20 , and was judged to not be significant.

Therefore no setpoint revision was made at that time. This technical evaluation does use the revised source term to calculate alarm setpoints, and the change is not significant as was assumed in 10080-UR(B)-508.

This change will be communicated to Radiological Operations, however the current alarm setpoints appear appropriate with not obvious change needed. If the revised alarm setpoints are used, then the revised CF11 values will also need to be used. Predicted monitor cpm at maximum Technical Specification activity concentrations:

Current c m Rev. 3 c m 1.35E+03 1.38E+03 3.45E+05 3.49E+05 The monitor engineering unit conversion factors (CF11 ): The monitor alarm setpoint values: Current µCi/cc Rev. 3 µCi/cc High 38.0 41.1 Alert 28.5 30.8 The calculated monitor indication that corresponds to an RCS activity concentration of 21 uCi/g is 2.98E+03 uCi/cc for the high range channel. Note that this is a proposed EAL value and does not include instrument error consideration.

This value is "offscale" with the low range monitor {range of 1.43E-3 to 1.43E+3 uCi/cc), so no EAL value is applicable to the low range monitor.

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation

Subject:

Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B REFERENCES

\. R No.: ERS-SFL-88-027

1. Unit 2 Technical Specification Amendment 101, Docket No. 50-412, 1999 2. Unit 2 NRC SER Chapter 4, Section 4.2.4.2, Online Fuel System Monitoring
3. Unit 2 UFSAR Chapter 4, Section 4.2.3.3, Fuel Rod Performance 3 7 4. Unit 2 UFSAR Chapter 11, Section 11.5.2.5.10, Reactor Coolant Letdown Monitor (High and Low Range) 5. SWEC Calculation 12241 UR(B)-410-1, Determine the Safety Limits for the Reactor Coolant Letdown High Range and Low Range Monitor 2CHS-RQl-101A

& B, 1987 6. Calc.ulation ERS-SFL-88-027 Rev. 1, Process Safety Limits and Alarm Setpoints for 2CHS-RQ101 A/8:1989 . 7. ICRP Publication 26, Recommendations of the International Commission on Radiological Protection, Pergamon Press, New York, Reprinted 1981 8. ICRP Publication 30, Limits for Intakes of Radionuclides by Workers, Pergamon Press, New York, 1978 9. Federal Guidance Report 11. Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, US EPA 521/1-88-020, 1988 10. Unit 1 Technical Specification Amendment 205, Docket No. 50-334, 1997 11. SWEC Calculation 12241 UR(B)-478, Design Reactor Core Inventory (3.96% Initial Enrichment) and Associated Equilibrium Primary and Secondary Coolant Activities for BVPS, 1999 12. SWEC Calculation 12241 UR(B)-479, Radiological Source Term for Accident Analyses -Composite Equilibrium Reactor Core Inventory (3.6% -7% Initial Enrichment) and Associated Design Primary and Secondary Coo.lant Activities for BVPS, 1999 13. Calculation ERS-JTL-99-005, Unit 1 Letdown Monitor (RM-1CH-101)

Alarm Setpoint Calculation, 1999 14. US NRC Regulatory Guide 1.105, Instrument Setpoints, Revision 1, 1976 15. BVBP-RP-0002, Radiation Monitor Alarm Setpoint Determination

16. SWEC Calculation 12241 UR(B)-432-2, Trip Setpoint Calculation for 8 Radiation Monitors Associated with ORMS Communication Loop #1, 1987 17. Calculation ERS-SFL-86-026, r9, Unit 2 ORMS Isotopic Efficiencies, 1995 18. The Health Physics and Radiological Health Handbook, Shleien, 8., Scinta, Inc, Silver Spring, Revised Edition, 1992 19. SWEC Calculation 10080-UR(B)-484, Primary and Secondary DesignfTechnical Specification Activity Concentrations Including Pre-Accident Iodine Spike Concentrations and Equilibrium Iodine Appearance Rates Following Power Uprate, 200299 20. SWEC Calculation 10080-UR(B)-508, Impact of Atmospheric Containment Conversion, Power Uprate, and Alternative Source Terms on the Alarm Setpoints for the Radiation Monitors at BVPS2 21. Calculation ERS-SFL-88-027 Rev. 2, Process Safety Limits and Alarm Setpoints for 2CHS-RQ101 A/B, 1999 Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation REVISION:

3

Subject:

No.: Page: Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B ERS-SFL-88-027 Attachment 1 8 Alarm Setpoint Methodology DISCUSSION This appendix describes the bases for the alarm setpoint methodology.

Only increasing value alarm setpoints are addressed.

A similar methodology could be described for decreasing value alarm setpoints, but these are not applicable to radiation monitoring.

USNRC Regulatory Guide 1.105, Instrument Setpoints

[1), provides a regulatory position on setpoints on systems important to safety. The guide provides the following definition of "systems important to safety": * ... those systems that are necessary to ensure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shutdown the reactor and maintain it in a safe condition, or (3) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guideline exposures of 10 CFR Part 100, Reactor Site Criteria .... " The BVPS Unit 2 UFSAR [2] contains a commitment to this regulatory guide, but the referenced discussion in section 7 of the UFSAR does not specifically address radiation monitors.

SWEC addressed RG 1.105 in the development of Unit 2 category 1 radiation monitor setpoints.

This issue was addressed by the Radiation Safety Committee in meeting 25-87[3] and a position paper was prepared on this issue [4]. While recognizing the need to consider instrument errors in determining alarm setpoints, this position paper concluded that the regulatory guide was (1) applicable to a subset of the Unit 2 monitors, (2) applicable to only those Unit 1 monitors installed in response to a Unit 2 licensing commitment, and (3) not applicable to effluent monitors (ODCM). This position paper was accepted by the RSC (BV-RSC-27-87) and approved by the OSC (BV-OSC-48-87).

Regulatory Guide 1.105 provides, in part: " ... The setpoints should be established with sufficient margin between the technical specification limits for the process variable and the nominal trip setpoint to allow for (a) the inaccuracy of the instrument; (b) uncertainties in the calibration, and (c) the Instrument drift that could occur during the interval between calibrations

.... " The methodology employed by SWEC was, as was this appendix, based on ANSl/ISA-567.04-1988, Setpoints for Nuclear Safety-Related Instrumentation

[5], which provides a means to accomplish the above. DEFINITIONS Safety Limit [SL] Analytical Limit [AL] Trip Setpoint [TSP] A limit on an important process variable that is necessary to reasonably protect the integrity of the physical barriers that guard against uncontrolled release of radioactivity

[5]. Safety limits are documented in the UFSAR, in technical specification bases, and in other design basis documentation.

Limit of a measured or calculated variable established by safety analyses to ensure that a safety limit is not exceeded (5). The difference between a safety limit and an analytical limit provides margin to account for process dependent effects such as (but not limited to) process delays, emergency generator sequencing, valve or damper closure times, and instrument response times. A predetermined value [of the monitored parameter]

at which a bistable device changes state to indicate that the quantity under surveillance has reached the selected value [5]. The difference between a trip setpoint and an analytical limit is the allowance provided to account for instrument uncerta.inty, instrument calibration uncertainty (and, if not addressed in the determination of analytical limit, process dependent effects).

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation

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Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B RE I I No.: 9 ERS-SFL-88-027 Attachment 1 Upper Setpoint Limit (USL) A predetermined value of the monitored parameter above the trip setpoint that , if exceeded during periodic surveillance testing , indicates unsatisfactory instrument performance.

The band defined between the trip setpoint and the upper setpoint limit is the allowance provided to account for instrument uncertainties such as setpoint drift, power supply drift, random response variation, deadband, etc. Operational Limit [OL] The maximum value that the monitored parameter may attain during normal operations, based on administrative controls, that will not result in the occurrence of an alarm. These quantities are illustrated on the figure below. Total Loop Uncertainties TLU =EA +PA +LA +SA + TA +DA Total Loop Uncertainties TLU =EA +PA +LA +SA + TA +DA MCALRMSP.DRW Normal Operation DETERMINATION OF ALLOWANCES Design Safety Limit Analytical Limit (AL) Upper Setpoint Limit (USL) -TA+DA TRIP SETPOINT (TSP) Operational Limit (OL) Environmental Allowance

[EA] Includes the effects of radiation, temperature , pressure , humidity , chemical sprays on the instrumentation.

EA should be determined for all safety related monitors expected to operate under accident conditions if the instrument vendor has indicated an accuracy under these conditions that differs from the accuracy expressed for operation under normal conditions. Applies only to QA Category 1 monitors.

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation 3

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No.: Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B ERS-SFL-88-027 Attachment 1 10 Leakage Allowance

[LA] Process Allowance

[PA] Calibration Allowance

[CA] Sensor Allowance

[SA] Drift Allowance

[DA] Tolerance Allowance

[TA] Includes instrument signal losses due to cable or penetration leakage or impedance.

Applies only to QA Category 1 monitors.

Includes effects associated with the measurement of the process parameter (e.g., sample line plateout, isokinetic sampling), errors associated with calculation of the process parameter by indirect measurements (e.g., determining flow from Dp measurements).

Includes errors associated with calibrations of the sensor and the readout rack, such as those related to the calibration standard, equipment, and method. Includes errors associated with the sensor and readout accuracy.

Considerations include: linearity; deadtime; energy response linearity; repeatability; power supply stability; temperature, pressure, and humidity changes; ADC/DAC errors, etc. Includes errors due to undesired changes in instrument response, over a period of time, that are independent of the instrument input or use environment.

The period of time is normalized to the period between instrument calibrations or surveillance testing. Includes administrative tolerances allowed for calibration and/or setpoint adjustment (e.g., adjust to within +/-xx% of xxxx cpm). The errors addressed by these allowances may be dependent or independent.

Dependent errors are summed algebraically.

Independent errors are summed using the root-of-squared-sums method. Prior to summing, all errors are normalized to a common base (e.g., percent of span, percent of full scale). Unit 1 calibration MSPs provide a tolerance of +/-10%. Unit 2 calibration MSPs provide a tolerance of +/-15%. Not all of these allowances are applicable to a particular monitor --only those applicable are considered.

Dependent errors (e.g., LA, CP), are not addressed explicitly if it is reasonable to conclude that readout (end-to-end) calibrations adequately compensate for these effects. In cases where one allowance envelopes a related allowance, only the most restrictive allowance is summed. For example, an instrument setpoint accuracy (i.e., SA) of +/-1% is considered enveloped by a tolerance allowance (TA) of +/-10%. The total instrument loop uncertainty (TLU) is the sum of the individual allowances.

Assuming LA, to be dependent, and the remainder to be independent:

TLU = LA+/- SQRT( EA2 + PA2 + CA2 + SA2 + DA 2+ TA 2) The trip setpoint equals: NOTE: In the following, %+ TLU refers to the total loop uncertainty in the under-response direction expressed in percent. %-TLU refers to the total loop uncertainty in the over-response direction expressed in percent. TSP = AL -(TLU x TSP) \ TSP= AL/ [ 1 + (%-TLU) /100) The upper setpoint limit (USL) (NOTE: See definition above.):

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation

Subject:

Process Safety Limits, Alarm Setpoints and EAL

  • Indicator Value for 2CHS-RQ101 A/B USL = TSP+ (TSPxDA) + (TSPxTA) USL = TSP[ 1 + SQRT(DA2 + TA2) ] The operational limit (OL): OL = TSP -(TLUxTSP)

OL = TSP[1-(%-TLU/100)]

No.: ERS-SFL-88-027 Attachment 1 1. USN RC, Instrument Setpoints, Regulatory Guide 1.105, USGPO , 11176 2. BVPS Unit 2 Updated Safety Analysis Report, 1990 3. Minutes of Radiation Safety Committee Meeting 25-87 _, 4. Applicability of RG1.105 to BVPS Radiation Monitors, ERS-SFL-87-036, 1987 5. ISA, Setpoints for Nuclear Safety-Related Instrumentation, ANSl/ISA-867.04-1988 Page: 11 6. Ficke, R, Instrument Setpoint Calculations, presentation at Sorrento Electronics ORMS User's Group Meeting, Fall, 1990 Beaver Valley Power Station Radiation 3

Subject:

No.: Page: Process Safety Limits, Alarm Setpoints and EAL ERS-SFL-88-027 12 Indicator Value for 2CHS-RQ101A/B Attachment 2 A B H J K L M 101AIB L.aN Rll'1g e guratim gJABnn etpo and T. S. Max. 'De nslv Car T. S.Max. Efficienc:v T.S. Max. "Oenslv ear T. S.Max. Eflicencv (uCilg) (glee) (uCUcc) (cpmcc/uCi) (cpm) (uCi/g) (g.lcc) (uCilcc) (cpm-cduCO (cpm) 3.89E-02 0.9867 3.84E-02 O.OOOE+OO O.OOE+OO Sr-92 9.79E-05 0.9867 9.66E-05 7.921E+o4 7.65E+OO 1.18E+01 0.9867 1.16E+01 O.OOOE+OO 0.00E+OO v.eo 5.64E-06 0.9867 S.56E-06 O.OOOE+OO O.OOE+OO 1.35E-01 0.9867 1.33E-01 O.OOOE+OO 0.00E+OO v.eom O.OOE+OO 0.9867 O.OOE+OO 3.535E+02 O.OOE+OO 9.00E-02 0.9867 8.BBE-02 2.718E+04 2.41E+o3 Y-81 4.54E*05 0.9867 4.4BE-05 2.515E+02 1.13E-02 2.52E-01 0.9867 2.49E-01 8.093E+04 2.01E+04 Y-81m 7.51E*05 0.9867 7.41E-05 O.OOOE+OO O.OOEiOO 7.25E.o3 09867 7.15&03 8.275E+04 5.92E+o2 Y-82 8.40E..()5 0.9867 8.29E-05 1.916E+o4 1.59Ei00 O.OOE+OO 0.9867 O.OOE+OO 6.292E+04 0.00E+OO 2t.SS 6.00E-05 0.9867 5.92E-05 1.043E+OS 6.17E+OO 4.84E-01 0.9867 4.78E-01 O.OOOE+OO O.OOE+OO t-b-95 6.09E-05 0.9867 6.01E-05 1.032E+OS 6.20E+OO 2.95E+01 0.9667 2.91E+01 O.OOOE+OO O.OOE+OO Mo-99 7.24E*02 0.9867 7.14E-02 1.852E+o4 1.32Ei03 3.99E-01 0.9867 3.941:-01 D.OOOE+OO O.OOE+OO Tc-99 O.OOE+OO 0.9867 O.OOE+OO O.OOOE+oO O.OOE+OO 9.16E-01 0.9867 9.04E-01 3.686E+03 3.33E+o3 Tc.S9m 3.88E*0'2 0.9867 3.83E-02 O.OOOE+oO O.OOE+OO 9.09E-02 0.9867 8.97E-02 0.000E+OO O.OOE+OO 5.67E-05 0.9867 5.59E-05 6.669Ei03 3.73E-01 1.BBE-02 0.9867 1.B5E*02 2.734E+03 5.07E+01 2.10E-05 0.9867 2.07E-05 O.OOOE+OO O.OOE+OO 6.36E-02 0.9867 6.2BE*02 3.957E+04 2.4BE+o3 Rh-106 2.33E*05 0.9867 2.30E-05 1.522E+o4 3.50E-01 2.74E-01 0.9867 2.70E-01 1.060E+04 2.B7E+o3 Ag-11()n O.OOE+OO 0.9867 O.OOE+OO 3.18BE+OS 0.00E+OO 1.0BE-01 0.9867 1.07E-01 2.831E+05 3.02E+04 Sb-124 O.OOE+OO 0.9867 O.OOE+OO 1.966E+05 O.OOE+OO 4.10E-01 0.9867 4.QSE..01 1.316E+04 5.32E+03 Ts-125m 4.2CE-05 0.9867 4.14E-05 O.OOOE+OO O.OOE+OO 6.00E-02 0.9867 5.92E-02 2.461E+05 1.46E+04 Ts-127 1.11E-03 0.9867 1.10E-03 O.OQOEof()()

O.OOE-+00 2.3BE-01 0.9867 2.33E-01 9.640E+04 2.24E+04 Te-129 1.3SE*03 0.9867 1.33E-03 1.154Ei03 1.54E+OO 3.SOE+oo 0.9867 3.45E+OO O.OOOE+OO O.OOE+OO Te-12911 , .37E*03 0.9867 1.35E-03 4.723E-t03 6.3BE+OO O.ODE+oo 0.9867 O.OOE+OO O.OOOE+OO O.OOE+oo T&-131 1.23E*03 0.9867 1.21E-03 2.143E.a4 2.60E+01 O.ODE+oo 0.9867 O.OOE+OO 8.154E+04 O.OOE+OO Te-131m 3.42E-03 0.9867 3.37E-03 1.365E+05 4.61E+02 9.30E-03 0.9867 9.18E-03 O.OOOE+OO O.OOE+OO Ts-132 2.85E*0'2 0.9867 2.81E-02 O.OOOEof()()

O.OOE<OO 4.BOE-03 0.9867 4.74E-03 9.833E+04 4.66E+o2 Te-133 B.32E-04 0.9867 B.21E-04 4.605E.a4 3.7BE+01 O.OOE+OO 0.9867 O.OOE+OO 1.301E+05 0.00E+OO Te-133m 1.85E*03 0.9867 1.B3E-03 2.037E+05 3.72E+02 3.60E-03 0.9867 3.55E-03 O.OOOE+OO 0.00E+OO Te-134 2.84E*03 0.9867 2.BOE-03 5.890E.a4 1.65E+02 9.00E-04 0.9867 8.8BE*04 8.444E+04 7.50E+01 Cs-134 5.74E*01 0.9867 5.66E-01 2.169E+05 1.23E+05 O.OOE+oo 0.9867 O.OOE+OO 1.759E+02 O.OOE+OO Cs-134m 4.19E-03 0.9887 4.13E-03 O.OOOE+OO O.OOE<OO 1.38E-02 0.9867 1.36E-02 1.006E+05 1.37E+03 Cs-135 O.OOE+OO 0.9867 O.OOE+OO O.OOOE+OO O.OOE<OO O.OOE+oo 0.9867 O.OOE+OO O.OOOE+OO 0.00E+OO Cs-136 1.42E-01 0.9867 1.40E-01 1.860E+05 2.61E+o4 1.59E-03 0.9867 1.57E-03 1.662E+05 2.61E+o2 Cs-137 3.60E*01 0.9867 3.55E-01 9.631E.a4 3.42E.a4 O.OOE+oo 0.9867 O.OOE+OO 2.039E+02 0.00E+oo Ba-137m 3.41E-01 0.9867 3.36E-01 1.01BE+05 3.43E+o4 O.OOE+OO 0.9867 O.OOE+OO 3.254E+04 0.00E+oo Ba-139 7.57E-03 0.9867 7.47E-03 3.124E+02 2.33E+OO O.OOE+OO 0.9867 O.OOE+OO 3.98BE+02 0.00E+OO Ba-140 3.89E-04 0.9867 3.B4E-04 O.OOOE<OO O.OOE<OO 1.53E-03 0.9867 1.51E*03 4.364E+04 6.59E+01 1.a-140 1.34E-04 0.9867 1.32E-04 1.221E+05 1.61E+01 7.17E-03 0.9867 7.07E*03 O.OOOE+OO O.OOE+OO Ce-141 5.87E-05 0.9867 5.79E-05 O.OOOEof()()

O.OOE+OO 3.55E-03 0.9867 3.SOE-03 9.626E+04 3.37E+o2 Ce-143 4.33E*05 0.9867 4.27E-05 1.367Ef04 5.84E-01 3.75E-04 0.9867 3.70E-04 6.924E+03 2.56E+OO Ce-144 4.45E-05 0.9867 4.39E-05 O.OOOEi{)()

O.OOE-+W 2.62E-01 0.9867 2.59E-01 3.352E+04 B.67E+03 Pr-143 5.46E-05 0.9867 5.39E-05 1.264E.Q3 6.B1E.Q8 1.49E-02 0.9867 1.47E-02 1.322E+05 1.94E+03 Pr-144 4.48E-05 0.9867 4.42E-05 2.461 E+03 1.09E-01 1.16E-03 0.9867 1.14E-03 7.616E+04 8.72E+01 t.p-239 6.60E-03 0.9867 6.51E-03 O.OOOE+OO 0.00E<OO 3.31E-04 0.9867 3.27E-04 1.410E+01 4.61E-03 Cs-138 9.76E-02 0.9867 9.63E-02 1.177E+05 1.13E.a4 1.37E-04 0.9867 1.35E-04 7.623E+04 1.03E+01 Ts-127m 3.2CE*04 0.9867 3.16E-04 1.291 E+01 4.0BE-03 4.87E+o1 4.81E+01 1.18E+05 1.69E+OO 1.67E-t00 2.31E+05 5.04E+01 -lOTALS-o4.97Eot01 -TOTALS. 3A9Et05 uCila RCS uCilcc 130 deaF Clll1l 0.9867 wee (based en leldCWl tef1'1'1:'a1ure of 130 degrees F) Col B & I val.I es from 12241-l.R(Bl-484 Table 9.2 ColD" ColB *Col C : Col K" Coll* ColJ Col C & J e 61.6 ltm'll"@130 degF I 62.43 lbm'ft' slaldard c 0.9867 Col E & L 1BlJes from ERSSFL-86-026 r3 ColfeColo*CoiE:

ColMeC01K*eo1L CF11 cak:ulalim:

CF11 cal-monitor acti.111v al T.S. lllil (\.Cfccl I mcrlltor c:ullllrale v.th RCS al T.S. lllit CClll!ll CF11 a 4.97E+D1 I 3.49E+05 1.43E.04 it:llcc-com uCilcc @ 130 degF cpm Ql1I uCl/c:c.e llll !Cl/cc Mentor lnllcaUon@0.35 ICl/9 DE 1-131 a 3.49E+05 x 1.43E*04 4.97E+01 Hltil alarm b1P setDOlnt llnclcatai wtth 21"/.lnstNTientemr lnclu:ledl

= 4.11E+D1 Alert alarm trlpse1pcl rt (75"1. of Ille Hlghsetpclnt wtth 21 %1nstNTientemr lnclu:led)

= 3.08E+01 Monltcr lnclcaUon

@Z1 1£1/g IE 1-131 14.66E+o1

  • (21 /0.35) = 2.98E+03 Note: The isotopes used are consistent with the original calculation and not all of the isotopes in UR(B)-484 are included.

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation

Subject:

Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B 101 ange urati>n rm T. s. Male. *oemitv Corr T. s. Maic. (uCVg) (glee) (t.O'/cc) 3.89E*02 0.9867 3.84E-02 1.18E+01 0.9867 1.16Ei01 1.35E-01 0.9867 1.33E-01 9.00E-02 0.9867 8.88E-02 2.52E-01 0.9867 2.49E-01 7.25E*03 0.9867 7.15E-03 Kr-90 O.OOE+OO 0.9867 O.OOEiOO Xe-131 m 4.84E-01 0.9867 4.78E-01 Xe-133 2.95E+01 0.9867 2.91Ei"01 Xe-133m 3.99E*01 0.9867 3.94E-01 Xe-135 9.16E*01 0.9867 9.04E-01 Xe-135m 9.09E-02 0.9867 8.97E-02 Xe-137 1.BBE-02 0.9867 1.856-02 e-138 6.36E-02 0.9867 6.28E-02 1-131 2.74E-01 0.9867 2.705-01 1-132 1.08E*01 0.9867 1.07E-01 1-133 4.10E*01 0.9867 4.05E--01 1-134 6.00E-02 0.9867 5.926-02 l-135 2.36E-01 0.9867 2.33E--01 H-3 3.50E+OO 0.9867 3.45Ei00 C*14 O.OOE+OO 0.9867 O.OOEiOO r-41 O.OOE+OO 0.9867 O.OOEi-00 CF-51 9.30E*03 0.9867 9.1 BE-03 Mn-54 4.SOE-03 0.9867 4.7 4E-03 Mn-56 O.OOEl-00 0.9867 O.OOEiOO F&-55 3.&0E-03 0.9867 3.55E-03 F&-59 9.00E-04 0.9867 8.88E-04 Co-57 0.00Ei"OO 0.9867 O.OOE-+00 Co-58 1.38E-02 0.9867 1.36E-02 co-SBm o.OOEtoo o.9867 o.ooe-+oo Co-60 1.59E-03 0.9867 1.57E-03 Co-60m O.OOE+OO 0.9867 O.OOEiOO Ni.OS O.OOE+OO 0.9867 O.OOE+DO Cu-64 O.OOE+OO 0.9867 O.OOE+DO Zn-65 1.53E*03 0.9867 1.51E-03 Br-83 7 .17E-03 0.9867 7.07E-03 Br-84 3.55E*03 0.9867 3.SOE-03 Br-85 3.75E-04 0.9867 3.70E-04 Rb-88 2.62E*01 0.9867 2.59E-01 Rb-89 1.49E*02 0.9867 1.47E-02 Rb-90 1.16E*03 0,9887 1.14E-03 Sr-89 3.31E*04 0.9867 3.27E-04 Sr-91 1.37E*04 0.9867 1.35E-04 4.87E+01 4.81E-+01 BlicienO/ (cpn-cc/uO)

O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.496E-t02 4.722E-t02 4.471E+D2 3.538E+D2 O.OOOE+OO O.OOOE+OO O.OOOE+OO 9.664E+OO O.OOOE+OO 1.525E+01 2.359E-+02 3.120E-+01 1.046E-+03 6.093E-+01 1.129E-+03 5.492E-+02 O.OOOE+OO O.OOOE+OO 4.824E+D2 O.OOOE+OO 4.294E-t02 6.348E+D2 0.000E+OO 4.B87E-t02 5.7435-01 4.227E+D2 O.OOOE+OO 9.753E+02 1.195E+OO 1.885E-+02 2.345E+OO 2.503E-t02 O.OOOE+OO 5.077E+D2 3.137E-+01 1.870E+02 7.277E+02 4.161E+02 6.843E-02 3.300E+o2 H (cim) o.ooE +00 O.OOE+OO Y-90 O.OOE+OO 1.33E-+01 Y-91 1.17Ei02 Y*91m 3.20E+OO Y-92 O.OOE+OO Zr-95 0.00E+OO f'b-95 0.00E-!00 l\fo-99 O.OOE+OO To-99 8.73E+OO To-99m O.OOE-!00 Rl-103 2.83E-01 Rl-106 1.48E+01 Rh-106 8.44Ei00 Ag-110m 1.11E+D2 Sb-124 2.46E-+01 T&-125m 6.68E+01 Ts-127 1.28E+02 T&-129 O.OOE-!00 T&-129m O.OOE+OO T&-131 O.OOE+OO T&-131m O.OOE+OO T&-132 2.03E+OO Ts-133 O.OOE+OO T&-133m O.OOE-!00 T&-134 4.34E-01 Cs-134 0.00E +00 Cs-134m 5.76E+OO Cs-135 O.OOE+OO Cs-136 1.53E +00 Cs-137 O.OOE+OO Ba-137m O.OOEfOO Ba-139 0.00E+OO Ba-140 3.78E-01 L.a-140 O.OOE +00 Ce-141 1.78E+OO Ce-143 1.16E-02 Ce-144 4.83Ei01 Pr-143 1.07Ei01 Pr-144 4.76E*01 2.23E*05 Cs-138 4.47E-02 T&-127m 5.68E+02 REVISI No.: ERS-SFL-88-027 Attachment 2 T.S. Male. J *oensitv Corr (!}'cc) 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 0.9867 K T.S.Max. (uCi'cc) 9.66E-05 5.S&E-06 O.OOE+OO 4.48E-05 7.41E-05 8.29E-05 5.92E-05 6.01E-05 7.14E-02 O.OOE+OO 3.83E-02 5.59E-05 2.076-05 2.30E-05 O.OOE+OO O.OOE+oO 4.14E-05 1.10E-03 1.33E-03 1.35E-03 1.21E-03 3.37E-03 2.81E-02 8.21E-04 1.83E-03 2.BDE-03 5.66E-01 4.13E-03 O.OOE+oO 1.40E-01 3.556-01 3.36E-01 7.47E-03 3.84E--04 1.32E-04 5.79E-05 4.27E-05 4.39E-05 5.39E-05 4.42E-05 6.51E-03 9.63E-02 3.16E-04 1.67Ei00 Page: L Emdencv (cpm-ccluCO 4.578E+02 O.OOOE+OO 1.125E+DO 1.481E-+OO O.OOOEiOO 9.876E+01 3.826E-+02 3.977E-+02 6.889E+01 O.OOOE-+OO O.OOOE+OO 1.734E+o1 O.OOOE+DO 4.900E+01 1276E+03 7.016E-+02 O.OOOE+DO O.OOOEi-00 5.112Ei00 1.591Ei01 9.294E+01 5.995E+o2 O.OOOE+OO 2.301E+02 9.227Ei02 2219E-+02 7.155Ei02 O.OOOE+DO O.OOOEiOO 9.073Ei02 2.906Ei02 3.072E+D2 1.828Ei00 O.OOOE-+00 6.601Ei"D2 O.OOOE+oO 4.596Ei"D1 O.OOOE-tOO 4.637E-06 1.049Ei01 O.OOOEi-00 6.765Ei02 3.758E-02 (uCi'g) 9.79E-05 5.64E-06 O.OOE+OO 4.54E-05 7.51E-05 8.40E-05 6.00E-05 6.09E-05 7.24E*02 O.OOE+OO 3.886-02 5.67E-05 2.106-05 2.33E-05 O.OOEHXl O.OOE+OO 4.206-05 1.11E-03 1.35E-03 1.37E-03 1.ZlE-03 3.42E*03 2.85E*02 8.32E-04 1.85E-03 2.84E*03 5.74E-01 4.19E-03 O.OOE+OO 1.42E-01 3.60E-01 3.41E*01 7.57E-03 3.89E-D4 1.34E*04 5.B7E-05 4.33E-05 4.45E-05 5.46E-05 4.48E-05 6.60E*03 9.76E-02 3.20E-04 1.69E+OO 6.04E+01 uCi'A RCS -lOTALS

  • 4.97E+01 *TOTALS* uCi'cc (al 130 deAF Densiycarecti:>n=

0.9867 g/cc (based on letcbv.n terrperatuie cl130degrees F) Ccl 8 & I valles from 12241-l.R(B}-484 Table 9.2 Ccl C& J =61.61bm'lt'

@130 degF /62.431bm'ft' S1al'llaltl=

0.9867 Cd D=Ccl B*Ccl c; Cd K= eo11*eo1J Cd E & l values Iran ERS-SR..*86-026 r3 CdF=Cdo*eoie; ColM=Co1K*cc1L CF11 calclllali:>n:

CF11 =at-monitor activity BIT.S. linit<uO/cc}I mrilor camt mtellith RCS at T.S. li"ni Ccpm} CF't 1 ,. 4.97E+01 I 1..38E+03 a 3.60E-02 uCl/cc.qim UCVa::'@130degF cpm epm ualcc-clllll ManllDrlnclcatlon@D.35uCUg DEl-131 = 1.38E+03 x 3.60E*02 a HiQh al arm triP set11oint Oncl cat kn with 21% t nstnment error In: ltmledl = Alert alann trip &etpolrt (75% d tht Hghsulpolrt with :Z1% lmtnment error ln:ltmled)

  • MonitDr lnclcation

@21 ICL'g DE 1-131 (4.66Ef01

  • (211 0.35) = uQ.lcc 4.97E+01 4.11 E+o1 3.0BE-t01 2.98E+03 Note: The isotopes used are consistent with the original calcufation and not all of the isotopes in UR(B)484 are included.

13 M (cpm) 4.42E-02 O.OOE-IOO O.OOE-IOO 6.63E-05 0.00E+OO 8.19E-03 2.27E-02 2.39E-02 4.92E-IOO 0.00E-IOO O.OOE-!00 9.70E--04 0.00E-IOO 1.13E-03 O.OOE-IOO 0.00E-!00 0.00E-IOO 0.00E-IOO 6.81E-03 2.15E-02 1.13E-01 2.02E+OO O.OOE+OO 1.89E-01 1.68Ei00 6.22E-01 4.05E-+02 O.OOE-IOO O.OOE-!00 1.27E+D2 1.03E+o2 1.03E+o2 1.37E-02 O.OOE-IOO 8.73E-02 OOOE-!00 1.96E-03 O.OOE+OO 2.50E*10 4.64E-04 0.00E+OO 6.51E+01 1.19E-05 8.14E-+02 CPITl

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