ML032760661

TVA Calculation 0-RE-90-102/103, Demonstrated Accuracy Calculation

ML032760661
Person / Time
Site:	Sequoyah
Issue date:	09/20/2003
From:	Eric Turner Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
-RFPFR, 0-RE-90-102/103, B87 030115 005
Download: ML032760661 (79)

Text

k I  ;-'I AN CALCULATION COVERSHEETICCRIS UPDATE 02- I l REV0 EDMStS NO. EDMS TYPE EDMS ACCESSION NO (N/A for REV, 0)

B87 900310 002 calculations(nuclear) ID8$y 0 :-.

C O')Z Calc The: Demonstrated Accuracy Calculation 0-RE-90-1 02/1 03 CALC ID TYUE ORG lPLANT BRANCH l< NUMBER lCUR REV l NMUtY CURRENT CN NUC

___________

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SON

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EEB

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O-RE-90-102/103 ________ _ _ _ __

REAICAION A PPLICA BILITY NEW CN NUC _ Entire calc 1 NEW_ CN___ _Selected pages O No CCRIS Changes 0 ACTION NEW EO DELETE 13 SUPERSEDE O3 CCRISUPDATEONLY . (For calc revision, CCRIS REVISION 1 RENAME EO DUPLICATE 13 (Verifier Approval Signatures Not Required) j been rviewed and no CCRIS changes required)

UNITS SYSTEMS . UNIDS 0 090 O-RE-90-102 and 103 IDCN.EDC.N/A APPLICABLE DESIGN DOCUMENT(S) CLASSIFICATION

-EDC2G9869A 2o g IASON-DC-Va9.0 I E QUALITY SAFETY RELATED? RIFIED SPECIAL REQUIREMENTS DESIGN OUTPUT SARITS AFFECTED RELATED? I(if yes, OR = yes) ASSUMPTION AND/OR LIMITING CONDITIONS? ATTACHMENT?

Yes 1 No O Yes O No IM Yes O No 13 Yes O No E3 Yes O No I9Yes 11 No O PREPARER ID PREPARER PHONE NO PREPARING ORG (BRANCH) VERIFICATION l NEW METHOD OF ANALYSIS Larry M. Begley 843 EEB METHOD El Yes l No Design Review PREPARERSIGNATURE 1 DATE CHECKER SIGNATURE DATE Latt 7Cs#-(1 7--q VERIFIER SiGNATURE ° j DATE APPROVAL SIGNAfURE

.. I V,-

/Vzo DATE z

STATEMENT OFPROBLEM/ABSTRACT J Problem Determine the accuracy of the subject instrument loops and demonstrate that the accuracy Isadequate for the intended purpose. Primary elements are located in a harsh environment. Subject devices are not part of PAM.

Abstract Calculations were performed to determine the accuracy of the subject Instrument loops. The determined accuracies were compared to the required accuracies, setpodnts, safety Emits and/or operating limits and the accuracy for the loops fisted below were demonstrated to be acceptable for the Intended function of the Instrument loops. This calculation applies to the Instrument loops listed below.

0-R-90-102 &103 MICROFICHE/EFICHE Yes El No E FICHE NUMBER(S)

O LOAD INTO EDMS AND DESTROY FI LOAD INTO EDMS AND RETURN CALCULATION TO CALCULATION LIBRARY. ADDRESS:OPS-1 8 O LOAD INTO EDMS AND RETURN CALCULATION TO:

TVA 40532 [07-2DO1 I Page 1 of 2 NEDP-2-1 [07-09-2001]

TVAN CALCULATION COVERSHEETICCRIS UPDATE

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CALC ID I TYPE I ORG I PLANT II BRANCH

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II NUMBER I REV

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I EEB I0-RE-90-1=2103 I I CN NUC I SON I I ALTERNATE CALCULATION IDENTIFICATION BLDG ROO l l ELEV lCOORDIAZIM l IR lPntewrt Yes O3 CATEGORIES l KEY NOUNS (A-add, D-delete)

ACTION KEY NOUN &R lKEYQNOUN CROSS-REFERENCES (A-add, C-change, D-delete)

ACTION XREF XREF XREF XREF XREF XREF (AICID) CODE TYPE PLANT BRANCH NUMBER REV A S DN SON EEB EDC 20896 A

_ _A _0317-01 Pa_ 2=f2ND--1[701 CCRIS ONLY UPDATES:

Following are required onl when makcing keyword/cross refnerne CCRIS update and pane I of form NEDP-2-1 Is not Incuded:

PREPARER SIGNATURE PREPARER PHONE NO.

DATE EDMS ACCESSION NO.

CHECKER SIGNATURE I DATE TVA 40532 (07-20011 Page 2 of 2 NEDP-2-1 [074)9-2001]

TVAN CALCULATION RECORD OF REVISION Page 2 TVAN CALCULATION RECORD OF REVISION Title DEMONSTRATED ACCURACY CALCULATION 0-RE-90-102/103 Revision DESCRIPTION OF REVISION Date No. Approved 0 Initial issue. The loops evaluated by this calculation were previously removed from the scope of calculation 0-RE-90-106A. This calculation supports resolution of SQ971511 PER.

Legibility Evaluated and Accepted for Issue: J. H. Rinne Date 6-7-00 This revision contains 97 pages.

This calculation was revised to incorporate a Safety Limit change defined in reference 6 MIN calculation for resolution of PER 02-003523-000 corrective action item 1.

Additionally, the Allowable Value defined within this calculation Is being added to the Tech Spec via Tech Spec Change 02-01. Reference 6 M/N calculation defines two Safety Limits based on utilizing either ICRP-2 or ICRP-30 methodology. Utilizing ICRP-30 methodology results in a relaxed or increased value for the Safety Limit. Therefore, utilizing this Safety Umit is desirable. However, NRC approval of Tech Spec Change 02-01 is required prior to use since this topic will be presented within the scope of the Tech Spec Change.

Based on the above discussion, this calculation revision will be prepared to support the Increased Safety Limit resulting from using ICRP-30 methodology defined within reference 6 MWN calculation. Whereas, an Appendix A will be provided that defines the current plant Setpoint and Allowable Value Limits necessary for compliance with the more restrictive Safety Limit defined within reference 6 M/N calculation based on ICRP-2 methodology until Tech Spec Change 02-01 receives approval by NRC.

Pages changed: 1,2,3,4,5,8,20,21,33-48,49-51,Attachment I sheets 1 and 2 Note: sheets 33-48 were totally reformatted using MathCAD and do not contain revision bars Pages added: IA,38A,45A, Appendix A, sheets 1-21, Attachment 9, sheet 1 Pages deleted: Attachment I sheet 3 Legibility Evaluated and Accepted for Issue: Date This revision contains 120 pages.

NEDP-2-1 (08-05-971 Page 2 of 3 TVA f08.97J 40532 10"71 WA 40532 Page 2 Of 3 NEDP-2-1 (08415-97)

Pace 3 TVAN CALCULATION VERIFICATION FORM Calculation Identifier 0-RE-90-102/103 Revision 1 Method of verification used:

1. Design Review E

2. Alternate Calculation a Verifier 441 ,fx Date _______

3. Qualification Test 01 /I I Comments:

This revision was performed to incorporate a Safety Limit change for resolution of corrective action item 1 of PER 02-003523-000 and also supports the Allowable Value defined within Tech Spec Change 02-01. All comments between myself and the preparer have been resolved. This calculation revision is found to be In compliance with NEDP-2. The FSAR compliance review has been performed as denoted by incorporation of the review form.

Additionally, the methodology utilized in this revision of the calculation is commensurate with the guidelines provided In Branch Technical Instruction EEB-TI-28, R5.

Page 1of 1 NEDP-2-4 [07-09.2001]

TVA 40533(07.20011 TVA 40533 [07-20011 Page 1of I NEOP-2-4 [074)9-20011

BRANCH/PROJECT IDENTIFIER O-RE-90-102/103. R1 DEMONSTRATED ACCURACY CALCULATION Page 4 FSAR COMPLIANCE REVIEW This review has been performed to verify FSAR compliance. The following FSAR sections have been reviewed:

5.2.7.1, 11.4.2.2,12.1.4, and 12.2.4 Tech Specs 3/4.3.1, 3/4.3.3, and 3/4.4.6 Results of review:

The SAR is impacted by issuance of this calculation.

Note: Tech Spec Table 3.3-6 and FSAR section 11.4.2.2.3 both specify a setpoint value of < 200 mR/hr. This setpoint is not conservative with respect to the results of this calculation since a new setpoint of

• 105.61 mR/hr is required. However, Plant Chemistry's procedure 0-SI-ICC-090-102.A maintains the setpoint at 50 mR/hr.

This condition is addressed within PER 02-003523-000. Therefore, the current Tech Spec and Safety Umit are both satisfied.

This calculation also defines an Allowable Value. The existing setpoint of < 200 mR/hr in Tech Spec Table 3.3-6 will be replaced with the Allowable Value via Tech Spec Change 02-01.

Prepared:. Date: By Checked:_

fJL% p Date:

/

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 TABLE OF CONTENTS A COVER SHEET ..................................................... 1 B. REVISION LOG..................................................... 2 C. DESIGN VERIFICATION FORM ..................................................... 3 D. FSAR COMPLIANCE REVIEW .................................................... 4 D. TABLE OF CONTENTS ..................................................... 5

1) PURPOSE ..................................................... 6

2) ASSUMPTIONS/REQUIREMENTS ..................................................... 6

3) SOURCE OF DESIGN INPUT INFORMATION (REFERENCES) ....................... 7-8

4) DESIGN INPUT DATA 4.1) DEFINITIONS & ABBREVIATIONS .................................................... 9-12 4.2) LOOP COMPONENT LIST .................................................... 13 4.3) LOOP FUNCTIONS, REQUIREMENTS & LIMITS ................................. 14 4.4) COMPONENT DATA .................................................... 15-18 4.5) COMPONENT DATA NOTES .................................................... 19-26

5) DOCUMENTATION OF ASSUMPTIONS .................................................... 27

6) COMPUTATIONS/ANALYSES 6.1) PROCESS UNCERTAINTY DISCUSSION/CALCULATION ..................... 28 6.2) WATERLEG UNCERTAINTY DISCUSSION/CALCULATION .................. 29 6.3) ACCURACY DISCUSSION................................................................30-31 6.4) ACCURACY CALCULATION INDEX & CALCULATIONS ..................... 32-48

7) SUPPORTING GRAPHICS 7.1) LOOPDIAGRAM .................................................... 49

8)

SUMMARY

OF RESULTS ..................................................... 50-51

9) CONCLUSIONS .................................................... 52

10) Appendix A ..................................................... ..53 l R1 Rev 1 Prep LMB Date 1-Sl-0o. Check F Date ( Sheet 5 c/o (fi Rev Prep Date Check Date Sheet c/o Rev Prep Date Check _ Date Sheet = c/o

i DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

1) PURPOSE The purpose of this calculation is a) to determine the accuracy of the instrumentation covered by this calculation, and b) to demonstrate that the instrumentation is sufficiently accurate to perform its intended function without safety or operational limits being exceeded.

2) SPECIAL CONDITIONS 2.1) ASSUMPTIONS X This calculation contains no assumptions.

NA The following assumptions were used in the performance of this calculation.

These assumptions require further analysis. This calculation may require revision if the assumptions below are shown to be invalid.

2.2 REQUIREMENTS

1) A Digital Volt Meter shall be used for calibration of the output device.

2) M&TE accuracy shall be better than or equal to one (1)times the accuracy of the device being calibrated.

3) The calibration cycle shall not exceed 18 months plus an allowable 25%

extension (22.5 months).

2.3 SPECIAL REQUIREMENTS NONE 2.4 LIMITING CONDITIONS NONE Rev Rev ___

o Prep LMB Prep Date *4'00 Check Date Check W Date Vu1m.. Sheet 6 Date Sheet c/o c/o 7

Rev _ Prep Date Check Date ____Sheet _ c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

3) SOURCE OF DESIGN INPUT INFORMATION (REFERENCES)

REF ATT REFERENCE (RIMS NO.)

I 1,2-47W600-2, R4 2 TVA Contract 72C61-92759 (General Atomics) 3 Design Criteria SQN-DC-V-21.0 (RI 3), 'Environmental Design" 4 1,2-47W605-1, RIO 5 Calculation 72186 RDM, RIO "A Review of Electronic Components in a Radiation Environment of <5xI04 RADS" (B43860721903) 6 1 Tl-RPS-1 81, R3 "Basis For Determining an Acceptable Setpoint For the RI Spent Fuel Radiation Monitor Setpoint" 7 EEB-TI-28, R5 (B43000229001) "Setpoint Calculations" 8 2 General Atomics Manual for RD-I E-I 15-185, Rev. 0,August 1973 9 3 SQNAPS3-100 "Demonstrated Range for the SQNP Radiation Monitors, Rev.12 10 4 General Atomics Manual Model RP-1, E-1 15-184, Rev. 2, June 1991 11 5 Letter to W. S. Raughley, TVA from Noel A Seefeldt/Don Peat 3-16-90 (B26900330903) 12 Master Equipment List (MEL)

Rev 1 Prep LMB Date ! L Check 4 Date 1/t.V/0. Sheet _ c/o g Rev Prep Date IICheck Date ___ Sheet _ c/o Rev = Prep Date Check Date Sheet = c/o -

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 3). SOURCE OF DESIGN INPUT INFORMATION (REFERENCES) (CONTINUED)

REF ATT REFERENCE (RIMS NO.)

13 6# etrfo olSed ersnatv o eea tmc/orno4 13 6 Letter from Noel Seefeldt Representative for General Atomics/Sorrento 4-16-90 (B2690051 1900) 14 TVA Contract 91 NNA-75801A 15 7 Letter from DL Koehl to MC Brickey for area radiation monitor SSDs, 7/17/90 16 8 General Atomics Radiation Monitoring Qualification Test Report, E-255-999, August 1981 17 SQN-OSG7-0033 Radiation Monitoring System NUREG 0588 Category and Operating Times, R1 3 18 Design Criteria SQN-DC-V-9.0 (R13), uRadiation Monitoring System" 19 Demonstrated Accuracy Calculation RE-90-275, R2 20 Demonstrated Accuracy Calculation 0-RE-90-106A, R11 21 Tech Spec Change TVA-SQN-TS-02-01 RI 22 9 Previous Calculation Cover Sheet(s)

Rev 1 Prep LMB Date L&6#4 Check f Date a4 Sheet t c/o j Rev Prep Date Check Date Sheet _ c/o Rev _ Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS Q-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.1) DEFINITIONS AND ABBREVIATIONS Aa ACCIDENT ACCURACY-ACCURACY OF A DEVICE IN A HARSH ENVIRONMENT CAUSED BY AN ACCIDENT Aas COMBINED ACCIDENT AND SEISMIC ACCURACY Ab ACCEPTANCE BAND-THE RANGE OF VALUES AROUND THE CORRECT VALUE DETERMINED TO BE ACCEPTABLE WITHOUT RECALIBRATION AB AUXILIARY BOILER LINE BREAK AF AFW PUMP TURBINE STEAM SUPPLY LINE BREAK AL ANALYTICAL LIMIT An NORMAL ACCURACY-ACCURACY OF A DEVICE LOCATED IN A ENVIRONMENT NOT AFFECTED BY AN ACCIDENT OR ACCIDENT OR PRIOR TO AN ACCIDENT As POST-SEISMIC ACCURACY AV ALLOWABLE VALUE CPM COUNTS PER MINUTE CV CVCS LETDOWN LINE BREAK De DRIFT INACCURACY Ebs BISTABLE INACCURACY Ect CURRENT TRANSMISSION INACCURACY Eed ENERGY DEPENDENCE INACCURACY Efa FIELD ALIGNMENT ERROR Rev 0 Prep LMB Date 5+-60 Check L Date ./4'oo Sheet 9 c/o 10 Rev _ Prep _ Date Check _ Date Sheet c/o Rev _ Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.1) DEFINITIONS AND ABBREVIATIONS (CONTINUED)

Eimp IMPRECISION- THE STATISTICAL UNCERTAINTY RESULTING FROM UNKNOWN RADIATION ENERGY LEVEL CONCENTRATIONS, WHICH AFFECT DETECTOR EFFICIENCY, COUPLED WITH THE RESPONSE TIME OF THE RATEMETER ELECTRONICS Encr NET COUNT INACCURACY Epc PRIMARY CALIBRATION ERROR HELB HIGH ENERGY LINE BREAK IAD INTEGRATED ACCIDENT DOSE ICRe INPUT TEST INSTRUMENT READING INACCURACY ICTe INPUT TEST INSTRUMENT CALIBRATION INACCURACY INDRe INDICATOR READING ERROR INDMe INDICATOR MOVEMENT ERROR IRe INACCURACY DUE TO CABLE LEAKAGE ISRe INPUT SOURCE RESISTANCE EFFECT L LOSS OF COOLANT ACCIDENT OR LOCA M MARGIN-THE DIFFERENCE BETWEEN THE SAFETY LIMIT/OPERATING LIMIT AND THE NORMALIACCIDENT ACCURACY (Mn=NORMAL MARGIN, Ma=ACCIDENT MARGIN)

MFe MAGNETIC FIELD EFFECT mR/hr MILLIREMS PER HOUR Rev 0 Prep LMB Date 5Lq/60 Check £gZ Date Sheet 10 c/o l/

Rev _ Prep Date Check _Date Sheet c/

Rev Prep Date Check Date Sheet = c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.1) DEFINITIONS AND ABBREVIATIONS (CONTINUED)

N/A NOT APPLICABLE OCRe OUTPUT TEST INSTRUMENT READING INACCURACY OPe OPERATING POSITION EFFECT OCTe OUTPUT TEST INSTRUMENT CALIBRATION INACCURACY PRCSe PROCESS UNCERTAINTY PSEe INACCURACY DUE TO POWER SUPPLY VARIATIONS PV PROCESS VALUE (ACTUAL)

RADe INACCURACY DUE TO ACCIDENT RADIATION EXPOSURE Re REFERENCE ACCURACY RH RHR LINE BREAK RNDe NORMAL RADIATION DOSE BETWEEN CALIBRATIONS Se INACCURACY FOLLOWING A SEISMIC EVENT SECu SPAN ERROR CORRECTION UNCERTAINTY SL SAFETY LIMIT SP SET POINT SPEe ZERO ERROR DUE TO EFFECTS OF OPERATING PRESSURE TAe TEMPERATURE EFFECT AT ACCIDENT CONDITIONS TID TOTAL 40 YEARS INTEGRATED DOSE TNe TEMPERATURE EFFECT IN THE MAXIMUM/MINIMUM ABNORMAL TEMPERATURE RANGES Rev 0 Prep LMB Date 5/q/00 Check Date 5//2/08 Sheet 11 c/o 12 Rev = Prep = Date Check Date Sheet c/o Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.1) DEFINITIONS AND ABBREVIATIONS (CONTINUED)

TPRe TEST POINT RESISTOR ERROR WLe WATERLEG UNCERTAINTY WLHP WATERLEG HIGH POINT WLLP WATERLEG LOW POINT Rev 0 Prep LMB Date AO$ Check Date 51,2/00 Sheet 12 c/o d Rev Prep Date Check Date Sheet _ c/o Rev _ Prep Date Check Date Sheet c/o__

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.2) LOOP COMPONENT LIST LOOP ID# COMPONENT ID#

0-R-90-102 0-RE-90-1 02 0-RM-90-1 02 0-RI-90-1 02 0-R-90-103 0-RE-90-1 03 0-RM-90-1 03 0-RI-90-1 03 Rev 0 Prep LMB Date A Check fW L Date Sheet 13 c/o If Rev _ Prep _ Date Check Date Sheet c/o Rev Prep Date Check Date Sheet _ c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.3) LOOP FUNCTION These loops are used to monitor gross radioactivity of the air space above the fuel pool area. When either of these redundant monitors detect a radiation level in the fuel pool area in excess of the setpoint, the monitors initiate isolation of the auxiliary building ventilation exhaust and startup of the auxiliary building gas treatment system (ABGTS). Reference 18.

LOOP REQUIREMENTS AND LIMITS:

RESPONSE TIME:

Based on the operators actions the process would change slowly with respect to the response time of the instruments electronics.

SAFETY LIMIT (Control Function and Alarm from Reference 6):

271.62 mR/hr (ICRP-2 methodology - refer to Appendix A computations) RI J 375.49 mR/hr (ICRP-30 methodology; applicable after NRC approval of TSC 02-01)

INDICATED RANGE:

1' to 104 mR/hr (Reference 9)

Per reference 9 the required range for area radiation monitors is 10-' to 104 mR/hr.

SETPOINT (BISTABLE):

Radiation monitoring setpoints will vary over the fuel cycle of the plant, however the error values will be given as constant and will not vary based on the setpoint.

The setpoint for this loop is controlled by Chemistry but must be maintained at RI

• 105.61 mR/hr (refer to Appendix A) for Tech Spec Compliance based on a Safety

J'mit'of 271.-62 mR/hr priorto-'NRC approval of Tech'Spdc&Charige 02-01.-

f~he setpoint, after'NRC approval-of reference 21 Tech"Spec Change for a Safety Limnit of 375.49 mR/hr, is

• 151 mR/hr. This calculation defines an Allowable Value that will replace the setpoint of

• 200 mR/hr defined in Tech Spec table 3.3-6 via Tech Spec Change 02-01.

Rev 1 Prep LMB Date / .Check Date 1LZ 4-Sheet /- c/o 1 Rev Prep Date Check Date Sheet c/o Rev = Prep Date Check Date Sheet = c/o -

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.4) COMPONENT DATA VALID FOR DEVICES IDENTIFIED ON SHEETS: 13 COMPONENT: 0-RE-90-102/103 CONTRACT #: 72C61-92759 REFERENCE #: 12 MANUFACTURER/MODEL: GENERAL ATOMICS/RD-1 REFERENCE # 2. 8 INPUT RANGE & UNITS: 10 1_104 mR/HR NOTE #: NA REFERENCE #: 8 OUTPUT RANGE & UNITS: PULSE SIGNALS NOTE #: 11 REFERENCE #: 8.11 OVERRANGE LIMIT: NA NOTE#: NA REFERENCE#: 8 CALIBRATEDSPAN: 10-'-i04mR/HR NOTE #:NA REFERENCE#: 8 ROOM # I PANEL #: Al3 / Fuel Pool Area NOTE #: NA REFERENCE #: 3 ELEVATION / COORDINATE: 734' / XA8 NOTE #: NA REFERENCE #: 1 MIN/MAXABNORMALTEMP: 40FF/110°F NOTE#: NA REFERENCE#: 3 ACCIDENT TEMPERATURE: 110"F NOTE #: NA REFERENCE #: 3 RADIATION TID (RAD): 3.5 X 104 RADS NOTE #: NA REFERENCE #: 3 RADIATION IAD (RAD): 2.09 x 103 RADS NOTE #: NA REFERENCE #: 3 INSTRUMENT TAP INFORMATION REFERENCE #: NA WLHP TAP ELEVATION: NA WLHP CONDENSING POT ELEVATION: NA WLLP TAP ELEVATION: NA WLLP CONDENSING POT ELEVATION: NA EVENT / CATEGORY / OPERATING TIME: NOTE #: NA REFERENCE #: 17 NA I NA / NA NA/ NA / NA NAi NA / NA NA NA / NA NA / NA / NA Rev 0 Prep LM[B Date Check D Date Q/Wg/D Sheet 15 c/o /6 Rev Prep Date Check Date Sheet c/o Rev = Prep Date Check Date Sheet = c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.4) COMPONENT DATA VALID FOR DEVICES IDENTIFIED ON SHEETS: 13 COMPONENT: 0-RM/RI-90-102/103 CONTRACT #: 72C61-92759 REFERENCE #: 12 MANUFACTURER/MODEL: SORRENTO ELECTRONIC IRP-1 REFERENCE #: 12 INPUT RANGE & UNITS: SEE NOTE NOTE #: 11 REFERENCE #: 10 OUTPUT RANGE & UNITS: SEE NOTE NOTE#: 12 REFERENCE#: 10 OVERRANGE LIMIT: NA NOTE #: NA REFERENCE #: NA CALIBRATED SPAN: 0-10 Vdc NOTE #: NA REFERENCE #: 10 ROOM # PANEL #: MCR/0-M-12 NOTE #: NA REFERENCE #: 12 ELEVATION / COORDINATE: 732'/C6-P NOTE #: NA REFERENCE #: 4 MIN / MAX ABNORMAL TEMP: 60°F / 104"F NOTE #: NA REFERENCE #: 3 ACCIDENT TEMPERATURE: 1040 F NOTE #: NA REFERENCE #: 3 RADIATION TID (RAD): 3.5 x 102 RADS NOTE #: NA REFERENCE #: 3 RADIATION IAD (RAD): <5 x 100 RADS NOTE #: NA REFERENCE #: 3 INSTRUMENT TAP INFORMATION REFERENCE #: NA WLHP TAP ELEVATION: NA WLHP CONDENSING POT ELEVATION: NA WLLP TAP ELEVATION: NA WLLP CONDENSING POT ELEVATION: NA EVENT / CATEGORY / OPERATING TIME: NOTE #: NA REFERENCE #: 17 NA / NA / NA NA / NA / NA NA / NA / NA NA / NA / NA NA / NA / NA Rev 0 Prep LMB Date f Check p Date 5 d Sheet 16 c/o (7 Rev Prep Date Check Date Sheet c/o Rev = Prep Date Check Date Sheet = c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.4) COMPONENT DATA (CONTINUED)

COMPONENT: RElRM/RI-90-102/103 PARAMETER VALUE/UNITS NOTE # REFE'RENCE #

Encr *14% of readina 1 11.19 Eed *15% of reading 3 13 Eimp 040.59% of readina 4 7.8.1109 I RI Ebs *1 %of reading 5 13 1

Ect NA 6 8.110.19 Epc *5% of readin 7 11 Re *3% of FS 13 10 TPRe NA 10 NJ

• 0.1% of FS (bistable)

ICTe *4% of readina(ratemeter) 14,15 _11.1 520 ICRe *4% of reading 14 11.1 5.20

• 0.1%of FS OCTe ratemeter & indicator 15 NJ OCRe NA 16 N

• 3% of FS (bistable & indicator)

Ab *3% of FS (ratemeter & ratemeterldetector) 2 37.10.11.15 Se NA 20 1E RNDe NA 17 3.5 RADe NA 17 3.5 TAo NA IS 8.11 WLe NA 21 NJ PRCSe NA 22 NJ

-1.58 of span INDRe +1.94%ofspan 9 7 mh IRe NA 19 3

• 0.1% of FS/ *C TNe Included in Re 2 3.7.110.11.15 INDMe ,2%

.

of FS (indicator) 8 13 Rev 1 Prep LMB Date Check IALI Date 34t 4Sheet 1I c/o If Rev _ Prep Date Check Date Sheet _ c/oo Rev ___ Prep Date Check _ Date Sheet co/_

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.4) COMPONENT DATA (CONTINUED)

COMPONENT:RE/RMIRI-90-1 02103 Efa NA 11

+11.08% of reading Ebd -10.89% of reading 23 19 Efac *5% of reading 24 11 Rev 0 Prep LMB Date

• Check fjl Date /z Sheet 18 c/o dI Rev Prep Date Check - Date Sheet _ c/o Rev Prep Date Check Date Sheet = c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.5) COMPONENT DATA NOTES COMPONENT:RE/RM/RI-90-1 02/103 NOTE I Encr is defined in reference 11 as detector environment with an accuracy of +/-14% of reading. Therefore, Encr = +/-14% of reading 2 Per reference 10, the ratemeter reference accuracy is +/-3% of equivalent linear full scale. All of the ratemeter errors are encompassed by this 3% error (Reference 11). This includes calibration inaccuracies, temperature effect, environmental effects and inherent equipment inaccuracies. Reference 10 states that temperature effect Is *0.1% of equivalent linear full scale / "C. The ratemeter Is located In the main control room, where the maximum temperature excursion is 16°C to 400C (reference 3). This would yield a temperature effect of:

Temp. Effect = +/-(40- 16C) x 0.1% x 10V

= *0.24 V Excluding this temperature effect would result in an inaccuracy of (0.3V - 0.24V = 0.06V). This 0.06V would still include other inaccuracies in addition to the reference accuracy. Per TI-28 (Reference 7), the acceptance band (Ab) should be at least equal to the reference accuracy. If the entire 0.06V were attributed to reference accuracy, Ab would equal 0.6% of equivalent full scale. However, to add more conservatism and minimize impact to existing plant procedures, Ab for the ratemeter and ratemeter/detector will be set equal to +/-3.0% of equivalent full scale, while the Ab for the bistable and the indicator will also be set equal to +/-3.0% of equivalent full scale. This value bounds the Ab value defined in reference 15 which states that the bistable and indicator have been repeatedly calibrated to *0.AV (1.0%).

3 Per reference 13 the vendor states the energy dependence (Eed) inaccuracy as +/-15% of reading from 70keV to 2MeV. Therefore the vendor number of Eed= +/-15% of reading is valid.

Rev 0 Prep LMB Date ____o Check Ws7 Date Sheet 19 c/o %2 Rev Prep Date I__ Check Date Sheet c/o =

Rev Prep _ Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.5) COMPONENT DATA NOTES COMPONENTREJRM/RI-90-102/103

1. t NOTE 4 Statistical uncertainty associated with counting the nuclear eventsill be greatest for the lowest countrate assuming equal time for counting. Imprecision is determined by calculating the standard deviation:

a=4RUT where R = countrate in cpm x detector sensitivityj T = 2RC (RC = time constant ofratemeter)

(RC varies withcountrate)

The setpoint will be determined by Chemistry for this loop and may vary during the fuel cycle of the plant. The sensitivity of the RD-1 detector as given In reference 8 is 120 cpm per mR/hr.

Using the time constants given In reference 10, precision was calculated over a range that will bound the setpoint. The following tabular data has been developed to identify the following terms for setpoints that vary from 10 to 1000 mR/hr. Whereas the maximum setpoint defined by this calculation is 151mRlhr. RI Setpoint x 120 2RC For a setpoint of 151 mR/hr;

_ 151(120)

- 2 (.00067) a = 3677.28 cpm 2a = 7354.56 cpm

% Error = (2a/(Setpoint x 120)) x 100

% Error = (7354.56 / (151 x 120)) x 100

%Error= 40.59 Setpoint + Error (mR/hr) = 151+ (2r /120) = 212.29 mR/hr or; Error= 212.29- 151= 61.29mR/hr Rev 1 Prep LMB Date e ,"Check t Date I Sheet Z' c/o2Lf Rev = Prep Date Check Date Sheet c/o Rev Prep Date Check Date ; Sheet = c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.5)\ COMPONENT DATA NOTES COMPONENT:RE/RM/RI-90-102/103 NOTE 4 (Continued)

Setpoint RC a(cpm) 2 c (cpm)  % Error Setpoint+ Error (mR/hr) Error (mRlhr) (mR/hr) 10 0.0033 426.40 852.80 71.07 17.11 7.11 20 0.0033 603.02 1206.05 50.25 30.05 10.05 30 0.0033 738.55 1477.10 41.03 42.31 12.31 40 0.0033 852.80 1705.61 35.53 54.21 14.21 50 0.0033 953.46 1906.93 31.78 65.89 15.89 60 0.0033 1044.47 2088.93 29.01 77.41 17.41 70 0.0033 1128.15 2256.30 26.86 88.80 18.80 80 0.0033 1206.05 2412.09 25.13 100.10 20.10 90 0.0033 1279.20 2558.41 23.69 111.32 21.32 100 0.0033 1348.40 2696.80 22.47 122.47 22.47 101 0.00067 3007.45 6014.91 49.63 151.12 50.12 102 0.00067 3022.31 6044.61 49.38 152.37 50.37 103 0.00067 3037.08 6074.17 49.14 153.62 50.62 104 0.00067 3051.79 6103.58 48.91 154.86 50.86 105 0.00067 3066.43 6132.86 48.67 156.11 51.11 106 0.00067 3081.00 6161.99 48.44 157.35 51.35 107 0.00067 3095.50 6190.99 48.22 158.59 51.59 108 0.00067 3109.93 6219.85 47.99 159.83 51.83 109 0.00067 3124.29 6248.58 47.77 161.07 52.07 110 0.00067 3138.59 6277.18 47.55 162.31 52.31 120 0.00067 3278.15 6556.30 45.53 174.64 54.64 130 0.00067 3412.01 6824.01 43.74 186.87 56.87 131 0.00067 3425.10 6850.21 43.58 188.09 57.09 132 0.00067 3438.15 6876.31 43.41 189.30 57.30 133 0.00067 3451.15 6902.30 43.25 190.52 57.52 140 0.00067 3540.81 7081.61 42.15 199.01 59.01 150 0.00067 3665.08 7330.17 40.72 211.08 61.08 151 0.00067 3677.28 7354.56 40.59 212.29 61.29 160 0.00067 3785.28 7570.56 39.43 223.09 63.09 170 0.00067 3901.78 7803.56 38.25 235.03 65.03 Rev 1 Prep LMB Date 1-l§4 Check f Date __ _&L Sheet 21c/o 22 Rev Prep Date Check Date Sheet c/o Rev Prep Date Check Date - Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.5) COMPONENT DATA NOTES COMPONENTRERM/Ri-90-1 02/103

1. NOTE I RI 5 Per Ref. 13, the trip circuit is highly stable and accurate with an absolute accuracy much better than 1%of reading. For conservatism, we will consider bistable error to be 1%or reading.

6 Ect - Current Transmission Error Current Transmission Error Isdiscussed In calculation 0-RE-90-1 06A (reference 20) and the information presented is applicable to the monitor loops in this calculation. Therefore, based on the information contained in reference 20, the error associated with current transmission is considered negligible.

7. Primary Calibration gpc)

Primary calibration is a procedure In which an NBS traceable source is used to generate a flux (dose rate) at a specified test location on the GA Technologies calibration range. The flux at this location Is measured with a calibrated ION source, whose calibration is traceable to an NBS ION chamber. The ION chamber or GM detector which Is undergoing calibration is then positioned at the same test location on the range and the response to the known flux (dose rate) recorded. Thus, each ION chamber and GM detector actually undergo a primary calibration. The error associated with this calibration is *5% of reading, per Ref. 11.

Epc = +/-5% of reading.

Rev 1 Prep LMB Date ZICheck l Date qLJJ 6As Sheet U.. c/o23 Rev Prep Date Check Date _ Sheet o c/o_

Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.5) COMPONENT DATA NOTES (CONTINUED)

COMPONENT:REIRM/RI-90-102/103

1. NOTE 8 Per reference 13, the movement error of the Indicator Is +/-2%. Therefore INDMe = +/-2% of full scale. The front panel indicator is not used for calibration of the bistable or computer, a DVM is used for these devices, therefore INDMe is not required for these devices.

9 Reference 7 requires the indicator reading error to be 1/2 the largest division on the scale.

The indicator scale is logarithmic which means that the reading error will vary depending on the which part of the decade the reading is taken. To obtain the reading in percentage of span the logarithm must be converted to decades an then to percent of span. The maximum reading error In the positive direction = Log(1.5) -Log(1.0) = 0.176 decades, while the maximum reading error in the negative direction = Log(2.0) - Log(1.5) = 0.124 decades. For the area radiation monitors, the scale is 5 decades (10.1 to 104 cpm). Therefore % span error equals:

0.176 decades err INDRe(+) = 5decades

= 0.035 error

= 3.5% of span 0.124 decades err INDRe(-) = 5decades

= -0.025 error

= -2.5% of span However, as shown by this table the positive and negative reading errors will vary throughout the readings on the decade.

Reading on Decade  % span error 2.0 - 3.0 +1.94% -1.58%

5.0 - 6.0 +0.83% -0.76%

7.0 - 8.0 +0.60% -0.56%

8.0 - 9.0 +0.53% -0.50%

Rev 0 Prep LMB Date S/fo' Check f Date 6 Sheet 23 c/o Xf Rev Prep Date Check Date Sheet c/o Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

4) DESIGN INPUT DATA 4.5) COMPONENT DATA NOTES (CONTINUED)

COMPONENT:RE/RM/RI-90-1 02/103 1/ NOTE 9 Cont.

The readability between the I and 2 divisions is approximately 10 times better than between 9 and 10, due to the physical size of the scale markings. Therefore, the operator is less likely to make a 112 division reading error on the larger scale divisions. Using this reasoning the reading error for the first scale division(between 1.0 and 2.0) will be taken as 1/4 divisions. Therefore positive reading will = Log(1.25) - Log(1.0) = 0.0969 decades, and the negative reading error = Log(1.25) - Log(11.5) = -0.0792 decades. Therefore % span reading error equals:

0.0969 decades err INDRe(+) = 5decades

= 0.0194 error

= 1.94% of span 0.0792 decades err INDRe(-) = 5decades

= -0.0158 error

= -1.58% of span It should be noted that these values for 1/4 division reading error between the I and 2 scale divisions are still more conservative than 1/2 division reading errors for the remainder of the decade scale division.

10 The test point resistors used for the calibration of this equipment are internal to the ratemeter and are accounted for In the accuracy, no additional error is needed for TPRe.

11 The RP-1 Area Monitor Ratemeter receives pulse signals from the radiation detector which in this case is a RD-1 Geiger-Mueller Tube and signal conditioning preamplifier. (Reference 11, Section 2.1) 12 Indicator 10-1 to 104 mR/hr Computer. 0.000 to 0.100 V dc Alarms: Two (2) DPDT relay contacts Calibration: 0 to 10 V dc Rev Rev 0 Prep LMB Prep Date 5/I%/'o Check Date Check a7 Date Date 6 Sheet 24 Sheet c/o c/o

__5 Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.5) COMPONENT DATA NOTES (CONTINUED)

COMPONENT:RE/RM/RI-90-102/103 NOTE 13 Per reference 10 the stated vendor reference accuracy is +/-3% of equivalent full scale.

14 Per reference 11 an NBS traceable source is used to generate a flux (doserate) at a specified dose location. Per reference 15, for calibration of the ratemeter, frequency calibrated uniform pulses are injected at the ratermeter input. The calibration of the ratemeter uses a pulse generator, counter and timer. Instrument maintenance calibration records (reference 20) have shown that a 4% variance in the desired pulse rate is achievable.

Therefore, ICTe and ICRe will be set equal to +/-4% of reading.

15 As a requirement of this calculation a digital voltmeter shall be used to read the output for the calibration of the ratemeter and indicator, while the DVM will be used to read the input for the calibration of the bistable. Instrument maintenance currently uses a Keithley 197 DVM which has a stated accuracy of 0.018% input + 0.00024 V over a range of 0-20 V dc. It is reasonable that any new DVMs will have an accuracy at least equal to the current DVMs.

Therefore to be conservative an error *0.1% of full scale will be used for OCTe for the ratemeter, and indicator and ICTe for the bistable.

16 The output reading device for the calibration of these devices is a DVM, which has no reading error. Therefore OCRe is not required.

17 The ratemeter and detector are located in a mild environment where the maximum radiation is 3.5 x 10 4 RADS (reference 3). Radiation effects are negligible for electronic components in a environment less than 5 x 104 RADS (Reference 5). Therefore RNDe and RADe are not required.

18 Per references 8, the maximum temperature the detector and ratemeter can operate in is 176°F, which is greater than the accident temperature of 1100F. Per reference 11, the reference accuracy includes any effects due to temperature while in the prescribed temperature ranges. Therefore TAe is not required.

19 The ratemeter and detector are located in a mild environment (Reference 3), therefore there is no error due to cable leakage effect.

Rev 0 Prep LMB Date Check L.t Date __l_/__ Sheet 25 c/o ___

Rev Prep Date Check Date Sheet c/o Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

4) DESIGN INPUT DATA 4.5) COMPONENT DATA NOTES (CONTINUED)

COMPONENT:RE/RMIRI-9O-1 02/103

1. / NOTE 20 Per reference 16, GA Seismic report, a seismic event will have no effect on the system.

Therefore Se is not required.

21 There is no waterleg error associated with this calculation. (See Section 6.2) WLe is not required.

Encl.

22 Process uncertainty is accounted for in XErOfor k this calculation. Therefore PRCSe is not required. As sas, 23 Per reference 19, bistable drift has been calculated using Sequoyah field calibration data.

Based on this data the drift associated with the bistable is +11.08% and -10.89% of reading.

24 Per reference 11, the factory alignment error, as stated by the vendor, is equal *5% of reading.

25 Field Alignment (Efa) is the uncertainty associated with calibration of the equipment in the field. The electronics are calibrated to the calibration source. The uncertainty of calibration, i.e., ICTe, ICRe, OaCTe, OCRe, and Ab. Thus field alignment error is not included as a separate term to conform with EEB-TI-28 convention.

Rev 0 Prep LMB Date eL/q/O Check z g Date 4 Sheet 26 c/o 2.

Rev Prep _ Date TT Check Date Sheet c/o Rev _ Prep Date Check Date Sheet c/_o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

5) ASSUMPTIONS There are no assumptions used in this calculation.

Rev 0 Prep LMB Date Check 7 Date X Sheet 27 c/o Z1 Rev Prep Date Check Date Sheet c/o Rev = Prep Date Check Date Sheet = c/o =

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

6) COMPUTATIONSIANALYSES (CONTINUED) 6.1) PROCESS UNCERTAINTY DISCUSSION/CALCULATION (CONTINUED)

X NO PROCESS UNCERTAINTY EXISTS FOR THIS CALCULATION X THE MEASURED PARAMETER ISTHE PARAMETER OF CONCERN; THEREFORE, PROCESS VARIATIONS ARE ACCOUNTED FOR INTHE DETERMINATION OF SAFETY AND/OR OPERATIONAL LIMITS.

OTHER: SEE DISCUSSION BELOW.

NA PROCESS UNCERTAINTY DOES EXIST AND IS DETAILED INTHE FOLLOWING DISCUSSION/CALCULATION.

Rev 0 Prep LMB Date 5AIO Check E Date Sheet 28 c/o I Rev Prep Date _____ Check DateA___ SheetL c/o Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

6) COMPUTATIONSIANALYSES (CONTINUED) 6.2) WATERLEG CALCULATIONS UNCERTAINTY DISCUSSION/CALCULATION X APPLICABLE TO ALL LOOPS LISTED ON SHEET 13 NA APPLICABLE ONLY TO LOOPS:

X WATERLEG UNCERTAINTY IS NOT CONSIDERED FOR THE CALCULATION BECAUSE:

X NO WATERLEG EXISTS FOR THIS CALCULATION.

NA THE EFFECTS OF WATERLEG CHANGES ARE INSIGNIFICANT. SEE DISCUSSION/CALCULATION BELOW.

NA OTHER SEE DISCUSSIONCALCULATION BELOW.

NA SEE SENSING LINE DIAGRAM ON SHEET OF THIS CALCULATION.

Rev 0 Prep LMB Date C Check j Date Sheet 29 c/o 36 Rev Prep Date Check Date Sheet c/o Rev = Prep -Date Check Date Sheet = c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

6) COMPUTATIONS / ANALYSES (CONTINUED) 6.3) ACCURACY DISCUSSION X The accuracy of this instrument for normal, post seismic and accident conditions will be determined by considering the parameters tabulated in the design input section of this calculation.

The accuracy calculation for seismic (As) is bounding for all seismic events.

X The square root of the sum of the squares method shall be used in this calculation for calculating accuracy since the factors affecting accuracy are independent variables.

X Bi-directional error and unidirectional error will be combined in a manner such that the sum of the positive uni-directional error will be added to the positive portion of the bidirectional error (obtained from the square root of the sum of the squares method), and the sum of the negative uni-directional errors will be added to the negative portion of the bi-directional error.

This method is conservative. Therefore, it will be used in this calculation.

Example: *10 = bidirectional error

+ 5 = first uni-directional error

- 2 = second uni-directional error Total Error = (+10 + 5) to ( 2) = +15 to -12 X All calibration requirements (M&TE accuracies, device acceptance bands, calibration frequency post-seismic calibrations etc.) selected and utilized in this calculation shall be reflected In Section 8 -

SUMMARY

OF RESULTS (SET POINT AND SCALING) for incorporation into the Set Point and Scaling Document. These values are validated through their use in this calculation when the loop acceptance criteria are met."

NA Other: NOT REQUIRED NOTE: All systems analysis based on or using accuracy values from this calculation should take into account the fact that operator action and/or automatic initiations may occur at a process value differing from the indicated or setpoint values by the amount of the calculated inaccuracies.

Rev 0 Prep LMB Date Check Date Sheet 30 c/o .3/

Rev Prep Date ___ Check Date Sheet c/o Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

6) COMPUTATIONS/ANALYSES (CONTINUED) 6.3) ACCURACY DISCUSSION (continued)

X THE FOLLOWING DEVICES ARE CALIBRATED INDIVIDUALLY. THEIR ACCEPTANCE BANDS ARE AS FOLLOWS:

DEVICE Ab REF.

0-RM-90-1 02/103 (ratemeter) +/-0.3V 3,10,11 0-RIWRI-90-102/103 (bistablefindicator) +/-0.3 V 15 X THE FOLLOWING DEVICES ARE CALIBRATED TOGETHER. THE ACCEPTANCE BAND FOR THE COMBINATION OF THESE DEVICES IS AS FOLLOWS:

DEVICE - Ab REFERENCE O-RE-90-1 02/103 +/-0.3V Section 4.5 0-RM-90-102/103 10,15 Rev 0 Prep LMB Date Check w Date S7/Ig71t Sheet 31 c/o 3i Rev = Prep Date Check Date I___Sheet c/_o =

Rev Prep Date Check Date Sheet c/oo

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

6) COMPUTATIONS/ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION INDEX 6.4.1 Ratemeter Ernor 6.4.1.1 Reference Accuracy Re 6.4.1.2 Output Calibration Test Error OCTe 6.4.1.3 Acceptance Band Ab 6.4.1.4 Input Calibration Test Error ICTe 6.4.1.5 Input Calibration Reading Error ICRe 6.4.1.6 Normal Measurable Accuracy Anftm 6.4.2 Ratemeter - Detector Error 6.4.2.1 Net count Rate Accuracy Encr 6.4.2.2 Primary Calibration Error Epc 6.4.2.3 Energy Dependence Error Eed 6.4.2.4 Factory Alignment Error Efac 6.4.2.5 Imprecision Error Eimp 6.4.2.6 Normal Measurable Accuracy Anf~RD 6.4.2.7 Normal Accuracy AnmxRD 6.4.2.8 Ratemeter/Detector Acceptance Band Abwm 6.4.3 Bistable Loop Error 6.4.3.1 Bistable Error Ebs 6.4.3.2 Input Calibration Testing Error ICTe 6.4.3.3 Acceptance Band Ab 6.4.3.4 Bistable Drift Ebd 6.4.3.5 Normal Measurable Accuracy Anfes 6.4.3.6 Normal Measurable Loop Accuracy LAnfes 6.4.3.7 Normal Loop Accuracy LAnes 6.4.3.8 Loop Accident Accuracy LAaes 6.4.3.9 Allowable Value AV 6.4.3.1 0 Setpoint Determination 6.4.4 Indicator Loop Error 6.4.4.1 Output Calibration Testing Error OCTe 6.4.4.2 Acceptance Band Ab 6.4.4.3 Indicator Movement Error INDMe 6.4.4.4 Normal Measurable Accuracy Anf, 6.4.4.5 Normal Measurable Loop Accuracy LAnf, 6.4.4.6 Indicator Reading Error INDRe 6.4.4.7 Normal Loop Accuracy LAn, 6.4.4.8 Loop Accident Accuracy LAa, Rev 0 Prep LMB Date 515/Do Check Date X Sheet 32 c/o 33 Rev Prep Date Check Date Sheet c/o _

Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-MO 021103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-1021103

6) COMPUTATIONS I ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.1 Ratemeter Module Error 6.4.1.1 Reference Accuracy (Re)

Re-%:=3.0 % of span Re:=Re% .10 volts 100 Re =0.3 volts 6.4.12 Output Calibration Testing Error (OCTe)

OCTe_% :=0.1  % eq. full scale OCTe: OCTe 2/ .10 volts 100 OCTe = 0.01 volts 6.4.1.3 Acceptance Band (Ab)

Ab_%:=3  % of Eq. full scale Ab_%

Ab:= - 10 volts 100 Ab = 0.3 volts Rev Prep Date l-1-i01 Check -9EV Date Sheet 33 c/o3f

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1021103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-O102/103

6) COMPUTATIONS /ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.1 Ratemeter Module Error (CONTINUED) 6.4.1.4 Input Calibration Test Error (ICTe)

ICTe :=4.0 % reading Per reference 13 the transfer function to equate a reading error Into an equivalent linear full scale error is:

% Reading error = -( 1 - 10+4-B(A)) x 100 where B = No. of decades / span and A = full scale error in volts Therefore, by arranging terms the reading error can be expressed in volts by the following equation:

ICTe._pos = LOG (1 + (%Reading/1 00)) / (No. Decades / Span) log I + LC1 ICTepos:00 ICTepos = 0.034 volts ICTe-neg = LOG (1 - (%Reading/1 00)) I (No. Decades I Span) log I ICTe)

ICTe neg = ( 10 0I)

(lo)

ICTeneg =-0.035 volts Rev I PrepI1L. Date 1-l Check E Date s/iio- Sheet 31- co 35

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/1 03 SEQUOYAH NUCLEAR PLANT BRANCHIPROJECT IDENTIFIER 0-RE-01 02/103

6) COMPUTATIONS I ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.1 Ratemeter Module Error (CONTINUED) 6.4.1.5 Input Calibration Reading Error (CRe)

ICRe = 4.0% of reading The error Is the same as ICTe which was calculated in section 6.4.1.4.

ICRepos:=ICTejpos ICRepos = 0.034 volts ICRe neg :=ICTeneg volts ICReneg =-0.035 6.4.1.6 Normal Measurable Accuracy (AnfRM)

AnfRM-pos :=4Re2+ OCTe 2 + Ab 2.+ ICTejpos 2 t ICRejpos2 AnSRM pos = 0.427 volts 2 2 2 AnfRM_neg :=Re+ OCTe 2 +/- Ab2 + ICTe neg .- ICRe-neg 2 AnfRM_neg =0.427 volts AnfRM can also be expressed in terms of % reading error based on the transfer function given in reference 13 (See Section 6.4.1.4).

Anf RM - lo f RM

-(Ios% Pas.O5) .100 AnfRMpos_% =63.514  % reading AnfjRM_neg2% _- IoAnfRMn-eg-0-5) 1 00 AnfRM_neg_% =-38.859  % reading Whereas, AnfRM = AnRM = AaRM (no unmeasurables)

Rev I Prep Date 1-1 0Check L Date 4b2° Sheet 35 c/ao 3

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADLATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-91 02/103

6) COMPUTATIONS / ANALYSIS (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.42 Ratemeter - Detector Error 6.4.2.1 Net Count Rate Accuracy (Encr)

Encr :=14 % of reading From the transfer function given in reference 13 (See section 6.4.1.4).

Encr_,pos = LOG (1+ (OReadingll 00)) / (No. Decades / Span)

Encr~pos: .- 0 (T50)

Encrpos=0.114 volts Encr neg = LOG (1 - (%Reading/1 00)) (No. Decades I Span) log( I- Encr Enlcr neg =

Encr_neg =-0.131 volts Rev j Prep Date 1-614 Check £? 1 Date A Sheet A C/o do

DEMONSTRATED ACCURACY CALGULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-9D-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-M1 02/103

6) COMPUTATIONS / ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error (CONTINUED) 6.4.2.2 Primary Calibration Error (Epc)

Epc :=5 % of reading From the transfer function given In reference 13 (See section 6.4.1.4).

Epcpos = LOG (1+ (%Reading/1 00)) / (No. Decades I Span)

Epc~pos:= 10 lo(I51 E)

Epc pos - 0.042 - volts Epcneg = LOG (1 - (OAReading/1 00)) (No. Decades I Span) log(, - PC)

Epc-neg:=

(1 )

Epcjneg =-0.045 volts Rev Prep 4 Date -1f- ' Checkf... Date Sheet 37 do 39

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-1 021103

6) COMPUTATIONS / ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.42 Ratemeter - Detector Error (Continued)

Energy Dependence Error (Eed)

Eed :=15 % of reading From the transfer function given in reference 13 (See section 6.4.1.4).

Eedpos = LOG (1+ (%Readingll 00))I (No. Decades I Span) log( +Eed Eed4pos:= 1001 T100/

Eed~.pos 0.121 volts Eedneg = LOG (1 - (%Reading/100)) / (No. Decades / Span) log(I1-Eed neg:= ( 00)

Eed-neg =-0.141 volts Rev I Prep Date 11'-I6 Check Date */ Seet 3 cC/o73

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-9O-102/103 SEQUOYAH NUCLEAR PLANT BRANCHIPROJECT IDENTIFIER 0-RE-90-1 02/103

6) COMPUTATIONS I ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6A.2 Ratemeter - Detector Error (CONTINUED).

6.4.2.4 Factory Alignment Error (Efac)

Efac := 5 % of reading From the transfer function given in reference 13 (See section 6.4.1.4)

Efacpos = LOG (1+ (%Readingll 00)) / (No. Decades I Span)

Elog( +-0)

EfCjpos:= (T100

- xfac..po=0.042 volts Efacneg = LOG (1- (%Reading/100)) I(No. Decades Span) log I - A5 Efac neg := )

Efacneg =-0.045 volts Rev ( Prep Datel Check ..EL4 Date .Sheet 3A-a 39

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1021103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

6) COMPUTATIONS I ANALYSIS (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.42 Ratemeter - Dector Error (CONTINUED) 6.42.5 Imprecision Error (Eimp)

Eimp_% :=40.59 % of reading lgl Eimp_ Io.

Eimp_pos :=

(~)

(10)

Eimppos = 0.296 volts Io~ Eirnp-Eimp_nAeg := (1E)

Eimp_neg =-0.452 volts 6.4.2.6 Normal Measurable Accuracy (Anf RMRD)

Anf RM RDpos:=JAnf RMpos2 + Encrpos 2 +EiMp_POS2 Anf RM RDjpos =0.532 volts Anf RM RD~neg :=4AnfRMneg2 + Encr neg + E2 p 2neg Anf RMRDneg =0.636 volts Note: The above AnfRM_RDpos and AnfRMRD neg terms represent the acceptable as found calibration tolerances With the input at the detector while monitoring the output at TP3 of the ratemeter.

Rev I Prep i Date I- /-- CheckU j. Date c/uc. Sheet 3. c/o do

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-9O-102/103

6) COMPUTATIONS I ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error (CONTINUED) 6.42.7 Normal Accuracy (AnRMRD)

AnjRMRD pos_:=4Anf RM RDpos2 + Epcpos2 + Eedos+ Efac_po AnRMRD.pos = 0.549 volts An_RMRDneg :=AnfLRMRDpneg 2 + Epc,_neg 2 + Eed_neg + Efacneg2 AnRMRDjnieg = 0.654 volts AnRMRD can also be expressed in terms of % reading error based on the transfer function given In reference 13 (See Section 6.4.1.4).

An_RM RD os % (I -

(_Ij 1D-- s.5). 100 AnRM RDvos % =88.121  % reading AnRMRD-neg-°%: =- (1 10-A , K_R"EL--0-.5) 100 AnRMRDneg% = -52.924  % reading RevL Prep Date Check Date Sheet 400 C/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error (CONTINUED) 6.4.2.8 Acceptance Band (Ab_RMRD)

Ab RM RD :=0.3 volts 6.4.3 Bistable Loop Error 6.4.3.1 Bistable Error (Ebs)

Ebs = 1.0% of reading From the transfer function given in reference 13 (See section 6.4.1.4)

Ebs (volts) = LOG (1+ (%Reading/1 00)) (No. Decades / Span)

\100 Ebs =8.643-101 volts 6.4.3.2 Input Calibration Testing Error (ICTe)

ICTee%:=0.1 % of FS or converting to volts; ICTe:= ICT-_o 10 100 ICTe =0.01 volts 6.4.3.3 Acceptance Band (Ab)

Ab%:=3  % of FS or converting to volts; Ab :=3- 10 100 Ab = 0.3 volts Rev Prep Date Check A Date Sheet /o {L Cl

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error 6.4.3.4 Bistable Drift (Ebd)

Sorrento Electronics the vendor of this equipment considers the only error associated with the bistable to be Ebs (See Section 6.4.3.1). All other errors are considered to be part of the reference accuracy of the ratemeter. However, Sequoyah in reference 19, using field data has been able to Isolate the error associated with bistable drift as

+11.08% and -10.89% of reading. To be conservative this value will be combined with the other bistable errors to yield a as-found value for calibration. From the transfer function given in reference 13 (See section 6.4.1.4).

Ebd (+volts) = LOG (1+ (%Reading/1 00)) I (No. Decades I Span) log I + 11.0)

(T10)

Ebd.pos = 0.091 volts Ebd (-volts) = LOG (1- (%Reading/l 00)) (No. Decades I Span)

Eineg : (10)]

Ebdneg =-0.1 volts Rev I Prep _ _ Date 1-04e-l Check a / Date I/4L Sheet.. c/ 3

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-1 02/103

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error (CONTINUED) 6.4.3.5 Normal Measurable Accuracy (AnLBS)

The bistable is calibrated by varying a potentiometer on the ratemeter. The detector and ratementer electronics are part of this calibration, therefore these errors are not included in the calculation of Anf.

Anf BSjos :=4Ebs2+ ICTe 2 + Ab2 + Ebdpos 2 Anf BSpos =0.314 volts Anf BS-neg '-Ebs 2+ ICTe2+ Ab 2+ Ebdneg?

Anf BSneg=0.317 volts 6.4.3.6 Normal Measurable Loop Accuracy (LAnfBS)

LAnf BSoPos:4AnfRM~p0s2+AnfBSpos + EnCrpos 2+ EiMppos2 LAnf BSjpos = 0.618 volts LAnf BSneg :=A RMneg2 + Anf BS neg2 *FEncr neg2 + Eimp neg LAnf BSneg = 0.71 volts 6.4.3.7 Normal Loop Accuracy (LAnBS)

BS~pos iLAnf..BS..pos2 4ed p6s 2 + Epc_pos2 Efacjsp LAnBS_pos =0.632 volts LAnBS neg:=4LAnfBSneg2+ Eedneg 2+ Epcneg 2+ Efacneg2 LAnBSneg =0.727 volts Rev I Prep Date 14-FfJ Check £it Date ./IL42x Sheet IL c/o ft

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-9O-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCHIPROJECT IDENTIFIER 0-RE-90-102/103

6) COMPUTATIONS /ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error (CONTINUED) 6.4.3.7 Normal Loop Accuracy (LAnrEBS) (CONTINUED)

LAn BS can also be expressed in terms of % reading error based on the transfer function given in reference 13 (See Section 6.4.1.4).

LAn.BSypose-% :=- (I - 10w SJ0-5) 100 LAn-BSPpos.8/%= 107.079 % reading LAn BSneg_%/e =- (I - 1OLAn BS_=gO.5) 100 LAnBSneg_% =-56.696 % reading 6.4.3.8 Loop Accident Accuracy (LAasBS)

LAa_BSjpos % :=LAn BSjns %

LAa_BS pos % = 107.079 % reading LAa_BS neg&% :=LAn BS neg %

LAaBS neg =-56.696 % reading 6.4.3.9 Allowable Value (AV)

The Safety Limit (SL) for the control function (initiate isolation of the auxiliary building ventilation exhaust and startup of the auxiliary building gas treatment system) is 375.49 mR/hr. This limit is converted to voltage as follows:

(SL mR .- 375.49"-

SLvolts :=2.(log(SLmR) + 1) fI`Slti 7.149 - - votts Rev4 Prep L Date 1-0-01 Check -zVI Date A Sheet 4 t c/oI j

DEMONSTRATED ACCURACY CALGULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-91 02/103

6) COMPUTATIONS /ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error (CONTINUED) 6.4.3.9 Allowable Value (AV) (CONTINUED)

Where:

Adbe :=LAnBSpos and Margin :=0.25 LAn BSpos Note: The margin of 25% of LAnBSpos is added for conservatism.

kV volts:= SL volts- ((Adbe- LAnf BSpos)+Margin)

P volts =-6.976 volts Converting to mR/br:

AAV volts-5)1 AV miR := 10 r IO AVnmR = 307.774 mR/hr Rounding down for conservatism of Tech Spec defined Allowable Value TeckSpecAV:=floor(AV mR)

TechSpecAV = 307 mR/hr AV without the addition of the Margin would be:

AV voltsnomargin :=SL_volts - ((Adbe - LAnf BSypos))

AV-volts_no_margin =7.135 volts and (AV volts noqmgin-5 AV mR no margin:= 10 lo AVmR nomargin =369.204 mRFhr This results in an AV margin of:

AVnmRnomargin- AV mR = 61.43 mR/hr or AV-voltsno_margin- AV volts = 0.158 volts Revs Prep Date - Check fi7 Date Sheet 45 c/o +54

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-901 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error (CONTINUED) 6.4.3.10 Setpoint Determination A maximum setpoint (SPjnax) value will be determined based on the value defined for AV in the previous section:

SP maxvolts :=AV volts- LAnf BS_pos SP-max-volts = 6.359 volts This value expressed In mR/hr is:

ISP ax volts-5\ 1 SP maxmR =10 10 J SP-maxnmR = 151.16 Where; SP-max-volts + LAn BS_pos = 6.991 volts or converting to mR/hr r1SP x= vos+ULAn BS PoS)-51-1 1O1 =313.014 mR/hr and SPmrax-voltS-An BS neg=5.632 volts or converting to mR/hr J(SP m volts-LIA BS g)-5] 6 8 10L 10 65.458 mR/hr Rev Prep I Date 1 CheckI£llf Date_______ Sheet1-4 6

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

6) COMPUTATIONSI ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.4 Indicator Loop Error 6.4.4.1 Output Calibration Testing Error (OCTe)

OCTe %:=0.1 %ofFS OCTe OCTc_°/e 10 100 OCTe =0.01 volts 6.4.4.2 Acceptance Band (Ab)

Ab_%:=3 %of FS Ab:= Ab_%. I%

100 Ab =0.3 volts 6.4.4.3 Indicator Movement Error (INDMe)

INDMe_%:=2.0  % of eq. FS INDMe= INDMe %/° Io 100 INDMe = 0.2 volts 6.4.4.4 Normal Measurable Accuracy (Anf.ind)

The indicator is calibrated by varing a potentiometer on the ratemete. The detector and ratementer electronics are not part of this calibration, therefore these errors are not included in the calculation of Anf ind.

Anf ind:=41NDMe 2 + OCTe 2 +Ab 2 Anf ind=0.361 volts Rev I Prep Date 1-0i-Q Checki ^l Date Sheet f do f

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-O-I02/103

6) COMPUTATIONSI ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.4 Indicator Loop Error (CONTINUED) 6.4.4.5 Normal Measurable Loop Accuracy (LAnf-ind)

LAnf indos:=4A RM RD AnRmd2 LAnf indjpos = 0.643 volts LAnf indjneg:=iAnf RMRD_neg 2 + Anfjind2 LAnf indjneg = 0.731 volts 6.4.4.6 Indicator Reading Error (INDRe) 1NDRepos% :=1.94 % of span INDRej~os INDRepos%10 100 INDRepos =0.194 volts INDRe~neg/o :=1.58 % of span INDRe neg INDRejneg%.§ 10 100 INDRe_neg 20.158 volts 6.4.4.7 Normal Loop Accuracy (LAn.ind)

LAn indpos :=4LAn indos2 + Eedpos2 + Epcqjos2 + Efacqos2 + INDRe pos2 LAn indjos = 0.685 volts LAn indneg:=4LAnf indneg2+ Eed neg? Epcqneg+ Efac neg + INDRe neg LAn_ind_neg - 0.764 volts Rev L Prep

• Date 1 tLL Check LILL. Date .1Ll4. Sheet 41 c/o 4-V

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-91 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90102/103

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.4 Indicator Loop Error (CONTINUED) 6.4.4.7 Normal Loop Accuracy (LAnjind) (continued)

LAn ind can also be expressed Interms of % reading error based on the transfer function given in reference 13 (See Section 6.6.1.4).

LAn indjpos% [II -_oo(LAnp-) o].I00 LAn-indjposfo = 119.998 % reading LAn id neg_% 1=-- I0 (-Ln-i0-ncI).O.5]o 1- 0 LAn ind.neg % =-58.492  % reading 6.4.4.8 Loop Accident Accuracy (LAa_ind)

LAa ind_pos% :=LAn indpos°/%

LAa indjpos% =119.998  % reading LAa ind-neg% LAnjind-nege/o LAaind-nego%=-58.492  % reading RevL Prep Date1Ž.6 L Checkf£AL Date c/lI0 Sheet 44 coi

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

6) COMPUTATIONSIANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 7.1) LOOP DIAGRAM X APPLICABLE TO ALL LOOPS LISTED ON SHEETS 13 NA APPLICABLE ONLY TO LOOPS: NA

\SD-)oz 9O-S 4 M-12 1 -21i14 ~

I M-12 ~ ~ i -1 -12 U1 'R-1S4 RU

-- --I L RU RI soiwso-ioz solozz 50103 s-ios mo-R-1t4 1/V fpw~ R-1S 3 LV/V 0_44R-163

- ---

102r I -12

-

t

---

M-1

-- I 1 i 1 R M-12 M 12 t0I2 2 2 t01 FUEL POOL RADIATION MONITOR O-RE-90-102 & -103 Rev 0 Prep LMB Date *-II-O Check _ Date 3 Sheet 49 c/o £0 Rev = Prep = Date Check Date Sheet _ c/o Rev Prep Date Check Date Sheet _ c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103

8)

SUMMARY

OF RESULTS (BISTABLE)

X APPLICABLE TO ALL LOOPS LISTED ON SHEETS 13 NA APPLICABLE ONLY TO LOOPS:

SAFETY LIMIT 7.149 (375.49 mRlhr)

MARGIN 0.158 (62.476 mR/hr)

PV = ACCIDENT 6.991 (313.014 mRlhr)

PV = SEISMIC NA PV = NORMAL 6.991 (313.014 mR/hr)

SETPOINTMAX* 6.359 (151.16 mR/hr)

PV = NORMAL 5.632 (65.458 mR/hr)

PV = SEISMIC NA PV = ACCIDENT 5.632 (65.458 mRlhr)

AVUPPER = 6.976 (307 mR/hr) + Aas = NA AVLOWER = NA - Aas = NA ALL VALUES SHOWN ARE IN Volts UNLESS NOTED OTHERWISE (REFER TO ACCURACY DISCUSSION, SECTION 6.4.3 FOR CLARIFICATION OF ABOVE)

• THE ERROR IN VOLTS IS CONSTANT OVER THE ENTIRE SPAN. THEREFORE THE ERROR AT THE BISTABLE SETPOINT WILL BE A CONSTANT %SETPOINT, REGARDLESS OF WHETHER THE SETPOINT REMAINS CONSTANT.

Rev 1 Prep LMB Date 4 Check 7 Date 7/o/6: Sheet 5° c/o 51 Rev Prep Date Check Date Sheet c/o Rev = Prep Date Check Date _ Sheet = c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

8)

SUMMARY

OF RESULTS (INDICATED)

X APPLICABLE TO ALL LOOPS LISTED ON SHEETS 13 NA APPLICABLE ONLY TO LOOPS:

REQUIRED ACCURACY NA MARGIN NA PV = ACCIDENT 119.998 PV = SEISMIC NA PV = NORMAL 119.998 RI INDICATED VALUE PV = NORMAL -58.492 PV = SEISMIC NA PV = ACCIDENT -58.492 MARGIN NA REQUIRED ACCURACY NA AVUPPER = NA +Aas= NA AVLOWER = NA -Aas= NA ALL VALUES SHOWN ARE IN % READING (REFER TO ACCURACY DISCUSSION, SECTION 6.4.4 FOR CLARIFICATION OF ABOVE)

Rev 1 Prep LMB Date 4-Check £fl Date _ Sheet j. c/o Rev _ Prep Date Check Date Sheet c/o Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUQYAR NUCLEAR PLANT SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

9) CONCLUSIONS X APPLICABLE TO ALL LOOPS LISTED ON SHEETS 13 NA APPLICABLE ONLY TO LOOPS: NA The demonstrated accuracy of +0.656 volts (+LAn) and -0.812 volts (-LAn) for bistable loops 0-R-90-102 and 103 will not result in challenging the upper safety limit of 271.62 mR/hr based on maintaining a bistable setpoint of < 105.61 mR/hr. However, the current setpoint for this loop must be maintained

• 105.61 mR/hr for compliance with the Safety Limit.

This maximum setpoint value allowed is less than the maximum allowed *200 mR/hr setpoint currently required by the Tech Specs. However, Plant Procedure 0-SI-ICC-090-102.A currently specifies the setpoint of 50 mR/hr. This condition is addressed within PER 02-003523-000. Therefore, the current Tech Spec and Safety Limit are both satisfied.

This Appendix to the calculation defines an Allowable Value of 221 mR/hr that will be in place until NRC approval of Tech Spec Change 02-01. Loop Indication for 0-R-90-102 and 103 does not have a required accuracy and is therefore determined to be acceptable.

Rev 1 Prep LMB Date q IZ OL Check 1 Date 9",ISheet 52- c/oo Rev Prep Date Check Date _ Sheet _ c/o Rev Prep Date Check _ Date Sheet c/_o -

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

1) PURPOSE The purpose of this appendix Is to determine the accuracy of the Instrumentation, setpoint requirements, and allowable value necessary for compliance with the safety limit of 271.62 mR/hr. This limit will be in place until NRC approval of Tech Spec Change 02-01.

Excerpts from the body of the accuracy calculation (mathCAD) have been incorporated within this appendix to formulate the provided results and summary.

Rev 1 Prep LMB Date Ljj<tCheck al7 Date . Sheet c /o _

Rev Prep Date Check Date Sheet c/o Rev Prep Date Check Date Sheet c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-9-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS I ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.1 Ratemeter Module Error 6.4.1.1 Reference Accuracy (Re)

Re-%:= 3.0 % of span Re:-=Ree.-10 volts 100 Re =0.3 volts 6.4.1.2 Output Calibration Testing Error (OCTe)

OCTe_% :=0.1  % eq. full scale OCTe: =0M2/_10 volts 100 OCTe =0.01 volts 6.4.1.3 Acceptance Band (Ab)

Ab_%:=3  % of Eq. full scale Ab:= Ab_ .10 volts 100 Ab =0.3 volts Rev I Prep Date-16L/O' Check 9L1LDate / Sheet 2- co 3

DEMONSTRATED ACCURACY CALGULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCHIPROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY UMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS / ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.1 Ratemeter Module Error (CONTINUED) 6.4.1.4 Input Calibration Test Error (ICTe)

ICTe :=4.0  % reading Per reference 13 the transfer function to equate a reading error Into an equivalent linear full scale error is:

% Reading error = -( 1 1 0+14-(A)) x 100 where B= No. of decades / span and A = full scale error in volts Therefore, by arranging terms the reading error can be expressed in volts by the following equation:

ICTe~pos = LOG (1 + (%Reading/1 00)) / (No. Decades I Span) log I + ICTe)

ICTepos := 100

_.pos:-~~~ I5 ICTejpos = 0.034 volts ICTe-neg LOG (1- (%Reading/1 00)) I (No. Decades / Span) log I- ICTe ICTe neg:= IW ICTe-neg =-0.035 volts Rev _Prep Date-1bi4-0 Check Date IbkL.. Sheet 3 Co___

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-1 02/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS /ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.1 Ratemeter Module Error (CONTINUED) 6.4.1.5 Input Calibration Reading Error OCRe)

ICRe = 4.0% of reading ThlC " tWM ICTe which was calculated in section 6.4.1.4.

-'--is ICRe-pos =0.034 volts ICRejneg :=ICTejneg volts ICReneg =-0.035 6.4.1.6 Normal Measurable Accuracy (Anf RM)

AofRM pos:=4R,?+OCTe2+Ab2 +ICTepos 2 + ICRe pos2 AofRMjos = 0.427 volts AnofRM_neg :=ReJ+12 OCTe ~ 2~+ Ab 2222

+ICTe-neg + ICRe neg AnfRM_neg =0.427 volts Anf RM can also be expressed in terms of % reading error based on the transfer function given in reference 13 (See Section 6.4.1.4).

AnLMPos °/:=- (I _ Io^nf RM-p--°1). 100 Anf RM_pos_% =63.514  % reading AnfRM neg.% =- (I _ ja-0n.5RM_ng45). 1oo AnfRM_neg_%/. -38.859  % reading Whereas, AnfRM = AnRM = AaRM (no unmeasurables)

Rev Prep Date 1- '4 OlOCheck sILL Date Sheet 4L c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-O- 021103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-9O-1021103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS /ANALYSIS (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error 6.4.2.1 Net Count Rate Accuracy (Encr)

Encr:=14 %ofreading From the transfer function given in reference 13 (See section 6.4.1.4).

Encr pos = LOG (1+ (%Reading/1 00)) ? (No. Decades I Span) log(, Encr)

T100 Encrjpos=0.114 volts Encr neg = LOG (1 - (0/oReading/1 00))/ (No. Decades Span) log(lI--\cr Encr -neg:=- 100/

(10)

Encrneg =-0.131 volts Rev / Prep Date _____Check .LL Date ./1Ll0. Sheet -5 CIo

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS / ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error (CONTINUED) 6.4.22 Primary Calibration Error (Epc)

Epc :=5 % of reading From the transfer function given in reference 13 (See section 6.4.1.4).

Epcjpos = LOG (1+ (%Reading/1 00)) / (No. Decades / Span)

Epcjpos:= ( lOPc)

Epc pos = 0.042 volts Epcjneg = LOG (1 - (%/Reading/100)) / (No. Decades / Span)

EpcAeg:= 10 I( IloEp)

Epc_neg = -0.045 volts Rev / Prep _____ Date Il..C,1Check .CI Date ______ Sheet o 7

DEMONSTRATED ACCURACY CALGULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-0-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-9O-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS /ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error (Continued)

Energy Dependence Error (Eed)

Eed :=15 % of reading From the transfer function given In reference 13 (See section 6.4.1.4).

Eedpos = LOG (1+(%Reading/1 00)) 1 (No. Decades / Span) loI1 Eed~

Eedpos := ( -100 Eed pos=0.121 volts Eedneg = LOG (1 - (%Reading/1 00)) (No. Decades I Span) log(I Eed)

Eed.neg:= \ 0/

Eedjneg=-0.141 volts Rev Prep Date 1I-rACheck_£ L Date II/LL Sheet C/o

DEMONSTRATED ACCURACY CALGULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS I ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error (CONTINUED).

6A.2.4 Factory Alignment Error (Efac)

Efac :=5 % of reading From the transfer function given in reference 13 (See section 6A.1.4)

Efac.pos = LOG (1+ (%Reading/1 00)) / (No. Decades / Span) logI(+ 5 Efac-,os:= ( 100 Efacjpos = 0.042 volts Efac_neg = LOG (1-(%/cReading/1 00)) I (No. Decades I Span)

Efac neg:= ( °°)

(5)

Efacneg =-0.045 volts Rev / Prep 911 Date 'b'T Check . L Date I/klQL Sheet c/o 9

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-M1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-1021103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS / ANALYSIS (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.42 Ratemeter - Dector Error (CONTINUED) 6.42.5 Impression Error (Eimp)

Einp_% :=48.67 % of reading (for setpoint of 105 mR/hr)

Eimpjos =[0( 0+)

Eimp_pos = 0.344 volts Einp neg:= ( 5 1Q Eimp_peg =-0.579 volts 6.4.2.6 Normal Measurable Accuracy (AnfRRD)

Anf RMRD-yos :=AnT RMpos 2 + Encr.._pos2+ Eimp 2os Anf RM RD pos = 0.56 volts Anf RMRDneg :=Anf RMneg + Encrneg + Eimp_neg2 Anf RM_RDneg =0.732 volts Note: The above AnfRMRD-pos and AnfRMRD neg terms represent the acceptable as found calibration tolerances with the input at the detector while monitoring the output at TP3 of the ratemeter.

Rev / Prep Date q/IZj Check £. j Date (liot Sheet 9Co °

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1021103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS/IANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error (CONTINUED) 6.4.2.7 Normal Accuracy (AnkRMRD)

An_RM RD pos: =Anf RMRDposF + EpcjposF + Eed pos2 + Efac pos2 An_RMRDjpos =0.576 volts AnRM RDjneg *4AnfJRMRDneg + Epcneg + Eednegi+ Efac neg AnRM RD neg = 0.748 volts AnRMRD can also be expressed in terms of % reading error based on the transfer function given in reference 13 (See Section 6.4.1.4).

AnRMRD-pos_% =- (1 -_ IJAn-9 RDp 05). loo AnRMRDpos_% = 94.199  % reading An-RM-RD-neg-%/6 =_(I _ la-ALRMRD-g 0 5).100 AnRM RDneg %/= -57.724  % reading Rev t Prep Date 7-kL5j Check £tl.Date /11b, Sheet c/o H

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-1021103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.2 Ratemeter - Detector Error (CONTINUED) 6.4.2.8 Acceptance Band (AbRMRD)

AbRMRD :=0.3 volts 6.4.3 Bistable Loop Error 6.4.3.1 Bistable Error (Ebs)

Ebs = 1.0% of reading From the transfer function given In reference 13 (See section 6.4.1.4)

Ebs (volts) = LOG (1+ (%Reading/1 00)) I (No. Decades I Span)

( )

logl +-

Ebs :=Ebs (50100 Ebs = 8.643 10> volts 6.4.3.2 Input Calibration Testing Error (ICTe)

ICTe% :=0.1 %ofFS or converting to volts; ICTe:= ICTeYo. 10 100 ICTe =0.01 volts 6.4.3.3 Acceptance Band (Ab)

Ab_%:=3 %ofFS or converting to volts; Ab :=- 10 100 Ab = 0.3 volts Rev Prep Date 1-L Check .IL Date Sheet cdo

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONSI ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error 6.4.3.4 Bistable Drift (Ebd)

Sorrento Electronics the vendor of this equipment considers the only error associated with the bistable to be Ebs (See Section 6.4.3.1). All other errors are considered to be part of the reference accuracy of the ratemeter. However, Sequoyah In reference 19, using field data has been able to isolate the error associated with bistable drift as

+11.08% and -10.89% of reading. To be conservative this value will be combined with the other bistable errors to yield a as-found value for calibration. From the transfer function given In reference 13 (See section 6.4.1.4).

Ebd (+volts) = LOG (1+ (%Reading/1 00)) 1 (No. Decades I Span) logl1+ 110)

Ebd 1o ( 100 Edpos:=- ( 10)

Ebdjpos = 0.091 volts Ebd (-volts) = LOG (1- (%Reading/1 00)) I (No. Decades I Span)

[d Ig (10 )]

Ebdneg =-0.1 volts Rev L Prep k Date 1-14-4 Check £L Date Sheet ! C/o -3o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 02/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS/ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error (CONTINUED) 6.4.3.5 Normal Measurable Accuracy (AnLBS)

The bistable is calibrated by varying a potentiometer on the ratemeter. The detector and ratementer electronics are part of this calibration, therefore these errors are not included In the calculation of Anf.

AnfBSpos :=Ebs2+ ICTe2 + Ab2 + Ebd pos2 AnfBSpos =0.314 volts Anf BSneg := 4 Ebs + ICTe +Ab + Ebd.neg Anf BSneg =0.317 volts 6.4.3.6 Normal Measurable Loop Accuracy (LAnfBS)

LAnf BSjpos :AnfRM.pos2 + Anf BSpos + Encrpos2 + Eimppos2 LAnf BSjPos =0.642 volts LAnfBSneg 4AnfRMneg + AnfBSneg2+ Encr neg 2+ Eimpneg LAnf BSneg =0.797 volts 6.4.3.7 Normal Loop Accuracy (LAn._BS)

LAILBS BS 2 2E2d LAnBS.~Pos :=4LAnfBSpos + Eedpos2 + Epcos2 + Efacpos2 LAnBSpos = 0.656 volts LAnBSneg:4LAnfBS neg + Eed neg + Epcneg2 + Efac neg2 LAnBS-neg = 0.812 volts Rev ( Prep 112L Date 1P/-11). Check-0I Date q/ll/O2 Sheet /3 c/o LfL

.PjWM,-- ls--.: -- - -- - -- -- - t .Y ACE 7 as no t_

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1021103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-1 02/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS / ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error (CONTINUED) 6.4.3.7 Normal Loop Accuracy (LAnpBS) (CONTINUED)

LAnBS can also be expressed in terms of % reading error based on the transfer function given in reference 13 (See Section 6.4.1.4).

LAnBS-posy :=_ (I _ j 0LAn BS p .). 100 LAnBS_pos % = 112.91 % reading LAn_BS neg % :=- (I _ i-d BS_O )-100 LAnBS neg_.%eo =-60.738 % reading 6.4.3.8 Loop Accident Accuracy (LAaBS)

LAaBS_pos_% LAnBSpos %

LAaBSjpos% = 112.91  % reading LAaBS neg% :=LAn_BSneg %

LAa-BS-neg_/o =-60.738  % reading 6.4.3.9 Allowable Value (AV)

The Safety Umit (SL) for the control function (initiate isolation of the auxiliary building ventilation exhaust and startup of the auxiliary building gas treatment system) Is 271.62 mR/hr. This limit is converted to voltage as follows:

SLmR:=271.62 SL-volts :=2. (og(SL_mR) + 1)

SLvolts = 6.868 volts Rev Prep Date 7i4 tCheck Fi Date Sheet /o (5 C*

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADUATION MONITORS 0-RE-90-1 02/1 03 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error (CONTINUED) 6.4.3.9 Allowable Value (AV) (CONTINUED)

Where:

Adbe :=LAnBSJos and Margin :=0.25.LAn BSpos Note: The margin of 25% of LAnBSpos is added for conservatism.

AV-volts = SL volts- ((Adbe- LAnf BSjpos) + Margin)

AV-volts 6.69 volts Converting to mR/hr:

(AVvolts 5\N AV mR:=10 10 /

AV mR = 221.236 mR/hr Rounding down for conservatism ConservativeAV :=floor(AVnmR)

ConservativeAV = 221 mR/hr AV without the addition of the Margin would be:

AV voltsnomargin := SL volts- ((Adbe- LAnf BSpos))

AV-volts_no_margin = 6.854 volts and

[AV volts no marin)5_

AV_mR_no._margin := l0k 10/

AVnmRnomargin = 267.242 mR/hr This results in an AV margin of:

AVmRno.margin - AVmR = 46.006 mRlhr or AVvolts_no_margin- AV-volts =0.164 volts Rev L Prep iii7 Date 17'FQc.Check_.EC1 Date Sheet /5 co

-- -- - -- ---- .--.

- -,R.. M-, M- - M. -71 --M - -

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-O102/103 APPENDIX A - EVALUATION FOR SAFETY UMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONSI ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.3 Bistable Loop Error (CONTINUED) 6.4.3.10 Setpoint Determination A maximum setpoint (SPmax) value will be determined based on the value defined for AV inthe previous section:

SPmaxvolts :=AV volts- LAnf BS_pos SP-max volts = 6.047 volts This value expressed in mRlhr is:

(SP ax volts\5_

SP-max-mR:=10 o10 SP max-mR = 105.61 Where; SP max volts + LAn BSpos - 6.704 volts or converting to mR/hr r(SP max volts+fLAn BS pos).5] _ 2 OL 10 J =224.86 mR1hr and SP-maxvolts- LAnBS-neg = 5.235 volts or converting to mR/hr r(SP max volts-LAn BS neg) 51 41.

RL1 10 J =41.466tSRlhr Rev f Prep Date C Checkg Date 5/llkSheet / c/o 7

- . ; - , -- - -- - -- -- -.- C. . ...- -- , . -- - .--- - .. I - - -

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-1 021103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LUMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.4 Indicator Loop Error 6.4.4.1 Output Calibration Testing Error (OCTe)

OCTe_%:=0.1  % of FS OCTe := OCTe-1.10 100 OCTe =0.01 volts 6.4.42 Acceptance Band (Ab)

Ab_%:=3 %ofFS Ab:= Ab_% 10 100 Ab = 0.3 volts 6.4.4.3 Indicator Movement Error (INDMe)

INDMe_%:=2.0  % of eq. FS XN~ INDMe_/

MNMe:= IN -e26 10 Io 100 INDMe =0.2 volts 6.4.4.4 Normal Measurable Accuracy (Anf ind)

The indicator Is calibrated by varing a potentiometer on the ratemete. The detector and ratementer electronics are not part of this calibration, therefore these errors are not included in the calculation of Anf ind.

2 Anf ind:= INDMet *OCTe 2 +Ab 2 Anf ind =0.361 volts Rev Prep i Date 7- I1-0ACheck .Date /ilaz Sheet / cIo (Y

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCHIPROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMu BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONS/ ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.4 Indicator Loop Error (CONTINUED) 6.4.4.5 Normal Measurable Loop Accuracy (LAnf ind)

LAnf ind pos :=AnLRMRDos2+Anf ind LAnf ind~pos =0.666 volts LAnf ind neg:=4AnfRMRD..neg +Anfind LAnf mdnneg=0.816 volts 6.4.4.6 Indicator Reading Error (INDRe)

INDRe pos_% :=1.94 % of span INDRe-pos =INDRe- os %10 100 INDReypos = 0.194 volts INDRe-neg_/o :=1.58 % of span INDRe neg= INDReneg2% 10 100 INDRe neg = 0.158 volts 6.4.4.7 Normal Loop Accuracy (LAnpjnd)

LAnmindjpos :=LAnfindos + Eedpos + Epcypos + Efac.posF + INDRepos' LAn ind-pos = 0.707 volts LAn ind neg:=JLAnf ind neg2 + Ee neg 2 + Epc neg2 + Efac neg2 + INDReIneg2 LAn indneg = 0.845 volts Rev I Prep guI Date 7IqFf- Check .3.1LDate Sheet IL. cIo

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-9102/1 03 APPENDIX A - EVALUATION FOR SAFETY LiMIT BASED ON ICRP-2 METHODOLOGY

6) COMPUTATIONSI ANALYSES (CONTINUED) 6.4) ACCURACY CALCULATION (CONTINUED) 6.4.4 Indicator Loop Error (CONTINUED) 6A.4.7 Normal Loop Accuracy (LAn_ind) (continued)

LAnInd can also be expressed in terms of % reading error based on the transfer function given in reference 13 (See Section 6.6.1.4).

LAn-ind-pos2/. :=-[I- j0(L~k:-d).0.] 100 LAn ind pos_% = 125.726 % reading LAn ind neg % :=-[1 - O(-LAninde-g).O.] 100 LAnindneg_% =-62.206 % reading 6.4.4.8 Loop Accident Accuracy (LAajInd)

LAa indpos % :=LAnindpos_%

LAa-indjpos_°% = 125.726  % reading LAaindneg_ 1/o =LAnindneg.%

LAa_indneg_%/o = -62.206  % reading Rev Prep Date i+ LCheck f Date Sheet/ C/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

8)

SUMMARY

OF RESULTS (BISTABLE)

X APPLICABLE TO ALL LOOPS LISTED ON SHEETS 13 NA APPLICABLE ONLY TO LOOPS:

SAFETY LIMIT 6.868 (271.62 mR/hr)

MARGIN 0.164 (46.76 mR/hr)

PV = ACCIDENT 6.704 (224.86 mR/hr)

PV = SEISMIC NA PV = NORMAL 6.704 (224.86 mR/hr)

SETPOINTmox* 6.047 (105.61 mR/hr)

PV = NORMAL 5.235 (41.466 mRlhr)

PV = SEISMIC NA PV = ACCIDENT 5.235 (41.466 mR/hr)

AVUPPER = 6.69 (221 mR/hr) + Aas = NA AVLOWER = NA - Aas = NA ALL VALUES SHOWN ARE IN Volts UNLESS NOTED OTHERWISE (REFER TO ACCURACY DISCUSSION, SECTION 6.4.3 FOR CLARIFICATION OF ABOVE)

• THE ERROR IN VOLTS IS CONSTANT OVER THE ENTIRE SPAN. THEREFORE THE ERROR AT THE BISTABLE SETPOINT WILL BE A CONSTANT %SETPOINT, REGARDLESS OF WHETHER THE SETPOINT REMAINS CONSTANT.

Rev 1 Prep LMB Date 1-'1I4?Check 7Date 7 Sheet 2-? c/o al Rev Prep Date Check _ Date Sheet c/o Rev Prep Date Check Date Sheet = c/o

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS 0-RE-90-102/103 SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER 0-RE-90-102/103 APPENDIX A - EVALUATION FOR SAFETY LIMIT BASED ON ICRP-2 METHODOLOGY

8)

SUMMARY

OF RESULTS (INDICATED)

X APPLICABLE TO ALL LOOPS LISTED ON SHEETS 13 NA APPLICABLE ONLY TO LOOPS:

REQUIRED ACCURACY NA MARGIN NA PV = ACCIDENT 125.726 PV = SEISMIC NA PV = NORMAL 125.726 INDICATED VALUE PV = NORMAL -62.206 PV = SEISMIC NA PV = ACCIDENT -62.206 MARGIN NA REQUIRED ACCURACY NA AVUPPER= NA + Aas= NA AVLowER NA -Aas= NA ALL VALUES SHOWN ARE IN % READING (REFER TO ACCURACY DISCUSSION, SECTION 6.4.4 FOR CLARIFICATION OF ABOVE)

Rev 1 Prep LMB Date _____ Check X Date i 'UN Sheet I c/o 2-Zi Rev Prep Date Check Date Sheet _ c/o Rev = Prep Date Check Date Sheet c/o

-U-- -

DEMONSTRATED ACCURACY CALCULATION FOR CONTROL ROOM AREA RADIATION MONITORS O-RE-90-102/103 SEQUOYAH NUCLEAR PLANT SEQUOYAH NUCLEAR PLANT BRANCH/PROJECT IDENTIFIER O-RE-90-102/103

9) CONCLUSIONS X APPLICABLE TO ALL LOOPS LISTED ON SHEETS 13 NA APPLICABLE ONLY TO LOOPS: NA The demonstrated accuracy of +0.632 volts (+LAn) and -0.727 volts (-LAn) for bistable loops 0-R-90-102 and 103 will not result in challenging the upper safety limit of 375.49 mR/hr based on maintaining a bistable setpoint of

• 151 mR/hr. However, the current setpoint for this loop must be maintained

• 151 mR/hr for Tech Spec RI Compliance.

This calculation defines an Allowable Value of 307 mR/hr that will replace the setpoint of

• 200 mR/hr defined in Tech Spec table 3.3-6 via Tech Spec Change 02-01. Loop Indication for 0-R-90-102 and 103 does not have a required accuracy and is therefore determined to be acceptable.

Appendix A of this calculation defines the Allowable Value and Setpoint requirements prior to NRC approval of Tech Spec Change 02-01.

Rev 1 Prep LMB Date / Check £rDate 4P Sheet 9j_ c/o -

Rev Prep Date Check Date Sheet _ c/o Rev Prep Date Check _ Date Sheet _ c/o

-t. T.AN CALCULATION COVERSHEETICCRIS UPDATE P .,? *Ti .2 t _

- .

-.

S... - 4 REV 0 EDMSIRIMS NO. l EDIMS TYPE: EDMS ACCESSION NO (WA for REV. 0)

NE 84120 237 calculatons(nudoar) B 8 7 020402 o0 s Cale TMe: Basis for Determining an Acceptable Setpoint for the Spent Fuel Pool Radiation Monitor Setpoint CALC ID TYPE P L BRANCH NUMBER CUR REV EW REVISION APPLICABILITY CURRENT ON SON NTB TIRPS181 R02 F. Entbre alW NEW CN Selected Pages3

_No CCRIS Changes El ACTION NEW DELETE D SUPERSEDE a CCRIS UPDATE ONLY , (For1carvision, CCRIS REVISION  ; RENAME a DUPLICATE D3 (D. V. & Approval Signatures Not i been reviewed and no j j Required) i CCRIS changes required)

UNITS SYSTEMS l NIDS 001002 go90 NA DCN.EDCNfA APPLICABLE DESIGN DOCUMENT(S) CLASSIFICATION EDC 2052A SQN4C-V-9.O I QUALITY SAFETY U NVERIFIED SPECIAL REQUIREMENTS ANDOR DESIG SARITS RELATED? RELATED? (If yes, ASSUMPTION LIMmNG CONDITIONS? OUTPT FFECTED Yes E No D QR - yes) Yes D No H Yes 0 No E ATTACHMENT?

PREPARER PHONE NO 751-4312 Yes0 I

I No PREPARING ORG (BRANCH)

Mechanical Design Q

DESIGN VERIFICATION METHOD Design Verification Yes D No Yes l No t

.

PREPARER S Doug Pollock

-

DESIGN VERIFIER SIGNATURE Marc C. Berg M .4d STATEMENT OF PROBLEMIABS The purpose of this-calculation is to determine the safety limit for the spent fuel pool radiation monitors. This calculation allows the use of a setpoint which will reduce or eliminate spurious trips and still not allow the safety limit to be exceeded.

The fuel pool area accident monitors (0-RE-90W102, 108) are provided to mitigate the offSite radiological consequences of a fuel handling aGidant Upon detecting a radiation lavel that is higher than the satpoint level, the monitors initiate isolation of the auxiliary building ventilation exhaust and startup of the auxiliary building gas treatnent system (ABOTS)- This calculation determines the relationship between the exposure rate seen by these monitors due to a postulated fuel handling accident and the resulting unfiltered site boundary thyroid dose. The exposure rate at the detector locations will be due primarily to the noble gasses released in the accident while the thyroid dose is a result of the iodine released. From the relationship between ofEfite dose and exposure rate at the monitors, a maximum offaite dose can be predicted from any monitor safety limit, thus an acceptable safety limit can be determined on the basis of the offsite radiological consequences of a fuel handling accident.

Four cores were analyzed, a conventional core at 1500 EFPD, and a TPC at 510, 1020, and 1530 EFPD. The results show the minimum ratio of the exposure rate seen by the detector at spent fuel pool to the resulting site boundary thyroid dose (based on ICRP-2 dose conversion factors) to be 9.0641 (mR/hrrem. This ratio is based on the exposure rate seen by the detector at the greatest distance possible for an accident in the pool. This is clearly conservative and it also does not require both detectors to be operable. Thus the results will be valid for a situation where ono of the two monitors is inoperable. Based on this ratio, a saety limit as high as (9.0541 mRlhr/remX30 rem) -Z7162E2 mRthr will be sufficient to keep the thyroid doer below 10% of the 10CER100 limit. That is, if one assumes sa scenaro in which the activity release results in an exposure rate at the detector less than 27L6Z mO/hr, which does not result In the isolation of the ventilation system, then the resulting site boundary thyroid dose wll not be greater than 20 rem. Note: The safety limit determined in this calculation does not take into account monitor Inaccuracies or Imprecision.

MICROFICHEIEFICHE Yes l No d FICHE NUMBER(S) TVA-F-T000947 D LOAD INTO EDMS AND DESTROY z LOAD INTO EDMS AND RETURN CALCULATION TO CALCULATION LIBRARY. ADDRESS:

rl LOAD INTO EDMS AND RETURN CALCULATION TO:

TVA 40532 j12-2000J Page 1 of2 NEDP-2-1 112-04-2000]

o No.

ttchnment i Identifier _-l

- he_~f_

Sheel..,.L/oL.A. I

DIi LCalculation No. TI-RPS4181 I Rev: 3 1Plant: SQN I Page: 16

Subject:

Basis for Determining an Acceptable Setpoint for the Spent Fuel IPrepared: 0 I Date: 3/a)h z

_

Pool Radiation Monitor Setpoint Checked: tj¶, I Date: 3-Iz-oz_

Results I Table 3 Site Boundary Thyroid Dose Due to an Unfiltered Release:

1500 EFPD Conventional Core 510 EFPD TPC 1020 EFPD TPC 1530 EFPD TPC ICRP-02 589.8 634.5 497.2 342.0 ICRP-30 426.7 458.8 359.6 247.4 Table 4 Exposure Rate Seen at Detectors Due to Release Case #1 Case #2 Case #3 Conventional core (1500 EFPD)

Detector #1 2.2970E+04 3.7594E+05 3.3775E+05 Detector #2 2.5284E-04 3.3266E+01 510 EFPD TPC Detector#1 2.5448E+04 4.2278E+05 3.7952E+05 Detector #2 2.8103E-04 3.6527E+01 1020 EED TPC Detector #1 1.9498E+04 3.2105E405 2.8835E+05 Detector #2 2.1601E.04 2.8148E+01  %%3DE+oj 1530 EFPD TPC Detector #1 I.S239E+04 2.1W4E+05 1.9449E+05 Detector #2 1.4699E-04 1.9202E+01 a, 5E~ o Table 5 The ratio of the exposure rate at the detector to the dose at the site boundary is:

1500 EFPD Conventional core:

ICRP-2 6.3778E+03mR/hr / 589.8 rem = 9.1180(mRlhr)/rem Safety Limit = 9.1180(mR/hr)/rem (30 rem) = 2.7354E+02 mR/hr ICRP-30 6.3778E+03mRhr / 426.7 rem = 12.6032(mR/br)*rem Safety Limit = 12.6032(mR/hr)/rem (30 rem) = 3.7810E402 mR/hr 510 EFPD TPC:

ICRP-2 6.0485E+03mR/hr 1634.5 rem = 9.6327(mR/hr)Irem Safety Limit = 9.5327(mR/hr)Irem (30 rem) = 2.8598E+02 mR/hr ICRP-30 6.0485E+03mR/hr / 458.8 rem = 18.1833(mR/hr)/rem Safety Limit = 13.1833(mR/hr)/rem (30 rem) = 3.9550E+02 mR/r 1020 EFPD TPC:

ICRP-2 4.5930E+03mR/hr / 497.2 rem = 9.2377(mR/hr)/rem Safety Limit = 9.2377(mR/hr)/rem (30 rem) = 2.7718E+02 mR/hr ICRP-30 4.5930E+03mR/hr / 359.6 rem = 12.7725(mldhr)/rem Safety Limit = 35.3277(niR/r)/rem (30 rem) = 3.8318E+02 mR/hr 1580 EFPD TPC:

ICRP-2 3.0965E+03mR/hr / 842.0 rem = 9.0541(mR/hr)Jrem Safety Limit = 9.0641(mR/hr)Irem (80 rem) = 2.7162E+02 mR/hr ICRP-30 3.0965E+03umRhr J 247.4 rem =12.5162(mRlhr)Jrem Safety Limit = 12.5162(mR/hr)/rem (30 rem) = 3.7649E+02 mR/hr The shaded values are the exposure rates at the detector location when the released activity reaches the surface of the pool in the case where the accident occurs in the corner of the pool farthest from the detector. This corresponds to the case in which one detector is inoperable. For an accident occurring at any other location in the pool, the detector will read higher than the shaded values when the released activity reaches the aurface of the I pool.

F-Attachment No. I Sheetw i. f 2 Identifier t-A2 qO- /la T1