ML072550245

GGNS Calculation JC-Q1E51-N635-1, Rev. 1, Instrument Loop Uncertainty and Setpoint Determination for Loops 1E51-N635A&E RCIC Pump Suction Transfer on Low CST Level (TS 3.3.5.2).

ML072550245
Person / Time
Site:	Grand Gulf
Issue date:	07/27/2006
From:	Entergy Corp
To:	Office of Nuclear Reactor Regulation
References
GNRO-2007/00061 JC-Q1E51-N635-1, Rev. 1
Download: ML072550245 (27)

Text

Attachment 4 To GNRO-2007/00061 GGNS Calculation JC-QIE5I-N635-1, Rev. 1

"' DRN No. Page(s) 31 CALCULATION (2) Initiating Doc.: CR-GGN-2006-0863 COVER PAGE [I DRN Superseded:

U- DRNs Voided:

0 Calculation SupersededNoided:

0 As-BulltINo ICN Required E] PendingllCN Required (Verify current status in IDEAS.)

0 CALCULATION (3) Reason For Pending Status: (ER, T.S., Change, etc.)

El DRN NIA (4) Calculation No: JC-QIE51-N635-1 (5) Revision: 1

'"'

Title:

Instrument Loop Uncertainty and Setpoint Determination for Loops 1E51-N635A&E RCIC Pump Suction Transfer on Low CST Level (TS 3.3.5.2)

(7) System(s): E51 & P11 to) Component/Equipment Identifier:

'") Safety Code: i~gJ Calc Code: IE51N035A/E 1E51 N635A/E 1E21K702 1E51F010 1E51F031 1PIlAO02 0 Yes (ANOIGGNS Only)

Ul Quality EJNo Setpoint (2°)Study Calc

[] YES 0 NO (1 t0CFR50.59 0 Review: Structure:

ElAddressed in Bldg. AUX. Elev.

El Attached Room Wall 0 No LBD Impact Coordinates:

• "' R-Type: J05.02 114) Org. Code: (ANO/GGNS/RBS Only) NPE-I&C Keywords: SetpointJ Topical Codes: (ANO Only)

REVIEWS Timothy M. Bryant /' 'M. Watson Gerald B. Lantz (1S( Name/Signature/Date Name/Signature/Date (18) Name/Signature/Date

[ Design Verifier Responsible Engineer U Reviewer SupervisorlApproval Ul Checker (Only As-Built DRNs included in Revision)

[] Comments Attached El Comments Attached

, __ENTERGY .

> CALCULATION SHEET SHEET 2 OF 26 CALCULATIONNO. JC-0IE5]-N635-1 REV. I CALCULATION BY Al DATE VERIFIED BY DATE 7Z 0 DRN 05-1571 (ER-GG-1999-0217) 1i CR-GGN-2006-0863 I.

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1*

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__~ ENGY CALCULATION SHEET SHEET 3 OF 26 CALCULATION NO. JC-OI E51-N635.-1 REV. I CALCULATION BY "*LS. DATE 1"/06ilo VERIFIED BY _j _DATE" 07fa CALCULATION CALCULATION NO: JC-Q1E5I-N635-1 Rev I REFERENCE SHEET I. DRNs INCORPORATED:

1.

2.

3.

4.

5.

II Relationships: Sht Rev Input Output Impact DRN/

Doc Doc Y/N Tracking

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0.nNo 0

1. see calc section 3.2

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III. CROSS

REFERENCES:

1. see calc section 3.1 IV. SOFTWARE USED:

Title:

N/A Version/Release: Disk/CD No.

DISK/CDS INCLUDED:

Title:

Version/Release Disk/CD No.

V. OTHER CHANGES:

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__ENTERG3Y R ' CALCULATION SHEET SHEET 4 OF 26 CALCULATION NO. JC-0IE5I-N635-1 REV. 1 CALCULATION BY -3a" 7f&7[

'iDTE VERIFIED BY ._L DATE

.TABLE OF CONTENTS SHEET COVER SHEET 1 RECORD OF REVISION 2 CALCULATION REFERENCE SHEET 3 TABLE OF CONTENTS 4 SECTION 1.0 PURPOSE 5 2.0 DESIGN REQUIREMENTS 5

3.0 REFERENCES

6 4.0 GIVEN 9 5.0 6.0 ASSUMPTIONS METHODOLOGY 13 14 I

7.0 CALCULATION 16 8.0 APPENDICES CONCLUSION 26 I

N/A ATTACH MENTS 1 ENGINEERING REVIEW FORM (1 sheet) 2 DESIGN VERIFICATION FORM (4 sheets)

ENTERGY

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CALCULATION SHEET SHEET 5 OF 26 CALCULATION NO. JC-Q1E51-N635-1 REV. I CALCULATION BY - DATE "l270I-Jo VERIFIED BY AAMDATE 077_7106 1.0 PURPOSE The purpose of this calculation is to determine the instrument loop uncertainty and limiting allowable values and setpoints for instrument loops 1E5 1-N635A&E in support of ER 1999-0217. The values generated by this calculation are in accordance with Ref.

3.1.1. Instrument loops 1E22N654C & G are addressed in Ref. 3.2.18.

2.0 DESIGN REQUIREMENTS The Reactor Core Isolation Cooling System (RCIC) is the primary makeup system to maintain reactor water level above the core when the reactor is isolated from its primary heat sink and its normal makeup, the feedwater system (Ref. 3.1.7). RCIC is initiated automatically on reactor low water level 2, or manually. The normal source of water for RCIC is the Condensate Storage Tank (CST) which contains reactor grade water (Ref.

3.1.4). However, low level in CST, or high level in the suppression pool, will initiate a transfer of suction to the suppression pool (Ref. 3.1.7 ).

For the RCIC system, CST level is sensed by two level transmitters (1E51-LT-N035A &

E) and two trip units (1E51-LIS-N635A & E) (Ref. 3.1.6 & 3.1.8). When tank level decreases to the setpoint, the trip units send a signal to the IE5 IF010 & 1E51F031 valve control logic to transfer RCIC pump suction from the CST to the suppression pool (Ref.

3.1.6 & 3.1.8). Since water in the suppression pool is not of reactor quality, this transfer is done only after all condensate sources have been exhausted or the suppression pool level is too high (Ref. 3.1.7).

The primary design consideration for the transfers is the maintenance of suction head on the RCIC pump (Ref. 3.1.3 & 3.1.7) which will ensure an uninterrupted flow of water to the reactor. The obvious analytical limit is the level of the vortex breaker of the suction piping which is 9" above the bottom of the CST. With instrument zero at 1' 1", this equates to -0.333 ft. (Ref. 3.2.10, 3.2.11 & 3.2.8) Because the transmitters will not function below instrument zero, the analytical limit would ordinarily be set equal to 0.0 ft.

In this case, however, the portion of suction piping that connects to the CST is non-safety related. Per 3.2.3, the instrumentation must be capable of detecting a suction pipe failure such that the suction swap to the suppression pool is completed before suction head is lost. For this to happen, the setpoint must be above the elevation of the top of the suction pipe. The analytical limit will therefore be set to equal to 3.0 ft, the indicated level of the top of the suction pipe. (Ref. 3.2.8)

RCIC is not considered an ECCS system and is not credited for credited for any DBA other than control rod drop accident (Ref. 3.1.34). However, the CST level transmitters for RCIC are required to function during all DBA's. Before the CST water is exhausted, the swap to the suppression pool must occur so that there is not a potential release path through the CST suction line.

CALCULATION SHEET

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SHEET 6 OF 26 CALCULATION NO. JC-O1E51-N635-l REV. 1 CALCULATION BY 1S36t . DATE 1 XTL/0b VERIFIED BY DATE 2 The RCIC system is designed in accordance with seismic Category I requirements; therefore, Loops IE51N635A&E have to function during and after a seismic event (Ref.

3.1.7). The postulation of an SSE and a LOCA at the same time is not required (Ref.

3.1.35). It is necessary to postulate a LOCA and a subsequent SSE or a SSE and a subsequent LOCA. Therefore, both seismic and LOCA effects will be included in this calculation.

It must be noted that per the Tech Spec (Ref. 3.1.5) there is no upper limit on the CST low level setpoint for the RCIC pump suction swap. The friction loss errors discussed in section 7.5 will result in the low level trip occurring earlier than desired. This will result in less usable CST volume. The 18 ft CST Tech Spec requirement (Ref. 3.1.32) only applies to HPCS in modes 4 or 5 when suction from the suppression pool is not available.

In this case the automatic swap would be disabled. The HPCS low CST level setpoint is addressed in Ref. 3.2.18. Per Ref. 3.1.34, the CST is not credited for RCIC except for station blackout. For station blackout 115,278 gallons of CST water is required. (Ref.

3.1.29) With the specified 4.Oft low level suction swap setpoint and 800 gpm RCIC flow, a usable volume of approximately 172,000 gallons will exist at the 22 ft CST low level alarm setpoint and a usable reserve volume of approximately 143,000 gallons will exist at the 18.9 ft level (bottom of CST standpipes). (Ref. 3.2.3)

3.0 REFERENCES

3.1 Cross References 3.1.1 Standard No. GGNS-JS-09 Rev 1, Methodology for the Generation of Instrument Loop Uncertainty & Setpoint Calculations 3.1.2 SDC-E22 Rev 2 (HPCS) 3.1.3 GE Design Spec Data Sheet 22A3124AJ Rev 18 (RCIC) 3.1.4 System Design Criteria SDC E51 Rev 2 (RCIC) 3.1.5 Tech Specs Table 3.3.5.2-1 3.1.6 J1270L-001 Rev 2 Loop Diagram 3.1.7 GE Design Spec 22A3124 Rev 5 (RCIC) 3.1.8 J1270-009 Rev 2 Logic Diagram 3.1.9 M-1065 rev 40, PI I P&ID

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,CALCULATION

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SHEET SHEET 7 OF 26 CALCULATION NO. JC-OIES1-N635-1 REV. I CALCULATION BY -- "t.ý DATE 7Z&21L VERIFIED BY A(K&4) DATE ,/7 6' 3.1. 10 J- 1506B Rev 1 Instrument Location El 119 3.1.11 A-001 Rev8PlanatEl 119 3.1.12 Passport EDB 3.1.13 J-0401 Rev 17 Upper Control Room Panel Location 3.1.14 A-0014 Rev 9 189' Control Building Floor Plan 3.1.15 FSK-I-1065-011-B Rev 7 3.1.16 GE PPD 164C5150 Sht 1 Rev 18, Sht 2 Rev 17, Sht 3 Rev 18 3.1.17 CR 1999-0481 3.1.18 Vendor Manual 460004044 3.1.19 CR 1999-0433 3.1.20 Tech Spec SR 3.3.5.2.4 3.1.21 Tech Spec SR 3.3.5.2.2 3.1.22 E 1185-043 Rev 3 3.1.23 TRM Table TR3.3.5.2-l 3.1.24 CR 97/1071-00 3.1.25 PER 91/6068 Rev 1 3.1.26 P&ID M-1083A, Rev. 33 3.1.27 NEDC-31336P-A, Class 3 September 1996, General Electric Instrument Setpoint Methodology 3.1.28 CRC Handbook of Chemistry and Physics, 57h Edition (pg. F-5) 3.1.29 UFSAR Appendix 8A.3

CALCULATION SHEET

-_- ENTERGY SHEET 8 OF 26 CALCULATION NO. JC-Q1E51-N635-1 REV. I CALCULATION BY "*'T) DATE 2A/L[4 VERIFIED BY _9 DATE 3.1.30 deleted 3.1.31 E1182-024 Rev 7 3.1.32 Tech Spec SR 3.5.2.2 3.1.33 Tech Spec Bases page B 3.5-18 3.1.34 EAR E99-018 Response 3.1.35 UFSAR 15.6.5.1 3.2 Relationships 3.2.1 Standard GGNS-E-100 Rev 5, "Environmental Parameters for GGNS" 3.2.2 MC-Q1E22-00010 Rev 1 3.2.3 ER 1999-0217-00 3.2.4 865E517-002, Rev. 14 DRN 05-384 3.2.5 Rosemount Instruction Manual 4247-1 dated 7/76 Trip/Indicator 460000047 3.2.6 Vendor Manual # 460001972 3.2.7 E51 MPL# 283X239BA Rev 18 DRN 05-433 3.2.8 J-1660B Rev 4 Level Settings Diagram DRN 05-1560 3.2.9 Vendor manual 460000944 Tab 20 3.2.10 C143.0-NIPI 1A002-1.3-17 rev 2, HPCS / RCIC CST Suction Nozzle 3.2.11 C143.0-NIPI 1A002-1.3-2 Rev 3, CST Vendor Drawing 3.2.12 J301.0-QS-27.0-15 Rev 0; Rosemount Low Dose Rate Radiation Test Report for 1153 Pressure Transmitters D8600063 3.2.13 06-IC-1E51-R-0002 Rev 103

CALCULATION SHEET

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SHEET 9 OF 26 CALCULATION NO. iJC-p1E5I-N635-1 .REV. I I CALCULATION BY --- T~ DATE 7 *1*o &VERIFIED BY XAW DATE Z7/

3.2.14 06-IC-I E5 1-Q-0002 Rev 102 /

3.2.15 Bechtel Calculation M5.6.007, Rev. 1, Sht. 781 3.2.16 MP&L Spec C196.0, Rev.5 3.2.17 J1660A Rev 3 Level Settings Diagram DRN 05-1559 3.2.18 JC-QIE22-N654-1 Rev 3 3.2.19 SC-1 E51 -LT-N035 Rev I Scaling Calculation 3.2.20 02-S-01-33 rev 18, Turbine Building Rounds 3.2.21 DCP 83/0108, added CST temperature monitoring instrumentation 3.2.22 MS-02 rev 50 3.2.23 SFD1065 rev 6 3.2.24 386X409BA rev 6, 1H13P601-21B EDL 3.2.25 163C1392 sht 1 rev 15 item 7, 1E51R600 flow controller PPD 3.2.26 04-1-01-E51-1 rev 123, RCIC SOl 3.2.27 06-OP- 1E5 I-Q-0003, rev 119, RCIC pump surveillance 4.0 GIVEN 4.1 Instrument Loop Block Diagram Transmitter Trip Unit Power P&ID Loop Dia.

I E5 I-LT-N035A,E 1E5I-LIS-N635A,E t E21-PS2 3.1.9 3.1.6

CALCULATION SHEET

_ ENTERGY SHEET 10 OF 26 CALCULATION NO. JC- IE51-N63 5-1 REV. I CALCULATION BY -fL+/- V DATE VERIFIED BY & DATE 0ZZ I

4.2 Transmitter Environment Description Data Reference Tag Number IE51 -LT-N035A,E Instrument Location:

Panel Local 3.1.6 Room IA201 3.1.10, 3.1.11 Environmental Conditions:

Normal:Zone N-032 3.2.1 Temperature 65-104F 3.2.1 Pressure 0.25 to 0 in.wg. 3.2.1 Radiation (Gamma) 3.5E2 rads (40 yr TID) 3.2.1 Humidity 50% RH 3.2.1 DBE or Accident: Zone A-057 3.2.1 Temperature 124F 3.2.1 Pressure 0.25 to 0 in.wg. 3.2.1 Radiation TID 2.77E4 rads (0.03 Mrads) 3.2.1 Radiation dose rate 9.91E2 rads/hr (0.00 1 Mrads/hr) 3.2.15 Humidity 50% RH 3.2.1 Seismic Conditions < 0.5g Assumption 5.2 Surveillance Intervals 18 months 3.1.5, 3.1.20 4.3 Trip Unit Environment Description Data Reference Tag Number I E5 1-LIS-N635A,E Instrument Location:

Panel 11H113-P629 3.1.6 Room 0C703 3.1.13, 3.1.14 Environmental Conditions:

Normal: Zone N-028 3.2.1 Temperature 60-90 OF 3.2.1 Pressure 0. 1 to 1.0 in wg. 3.2.1 Radiation (Gamma) 1.8E2 rads (40 yr TID) 3.2.1 Humidity 50% RH 3.2.1 DBE or Accident: Same as Normal 3.2.1 Surveillance Intervals 92 days 3.1.5, 3.1.21*

• The Tech Spec (Ref. 3.1.21) requires a channel functional test be performed every 92 days. The implementing procedure (Ref. 3.2.14) is actually a trip unit calibration.

-~- ETERGYCALCULATION SHEET SHEET 11 OF 26 CALCULATION NO. JC-0IE51-N635-1 REV. I CALCULATION BY "rImTh* DATE -1 t*.'tob VERIFIED BY ,ff1iL DATE 4.4 Transmitter Vendor Data Description Data Reference Tag Number 1E51-LT-N035A,E Manufacturer Rosemount 3.2.3, 3.2.7 Model 11 53GB5PA 3.2.3, 3.2.7 URL 62.5 ft (750 inwc) 3.2.6 Span 39.8 1ft (14.24" to 491.91") 3.2.19 39.8 1ft (14.26" to 491.94") 3.2.19 Accuracy: +/-0.25% span 3.2.6 Drift: +/-0.25% URL per six months 3.2.6 Power Supply: <0.005% span per volt 3.2.6 Temperature: +(0.75% URL + 0.5% span)/IOOF 3.2.6 Humidity: Sealed unit - no effects 3.2.6 Radiation: N/A 5.8 Static Pres: N/A for gage pressure transmitter 3.2.6 Seismic: +/- 0.25% URL for 3 g 5.2 Overpressure: <+/-0.25 URL for 2000 psi 3.2.6 Output Range 4-20 madc 3.2.6 4.5 Trip Unit Vendor Data Description Data Reference Tag Number IE5 i-LIS-N635A,E Manufacturer Rosemount 3.2.4, 3.1.16 Model 51ODU or 71ODU Assumption 5.6 Repeatability: +/-0.2% span 3.2.5, Note 1 Drift: +/-0.2% span per 6 months 3.2.5 Input Range 4-20 madc 3.2.5

NCALCULATION SHEET IULAENTERGY D E .oVREB z SHEET 12 OF 26 CALCULATION NO.

ICALCULATION BY "x,/ JC-QE51-N63-I DATE -71*.lth (VERIFIED "

BY Kt)DATE REV. I j*

• e Note 1: Table 5 of Ref. 3.2.5 defines environmental conditions at the Trip Switch in terms of "operating condition" and "environment." Conditions in Zone N-028 are bounded by line 2 defined as "adverse operating conditions" and "normal environment" The corresponding line on Table 6 specifies repeatability under the defined conditions as

+/-0.2%. This repeatability is valid for 6 months operation. An allowance for power supply effects, temperature effects, humidity effects and radiation effects are included in the repeatability.

4.6 Power Supplies Power Supply Tag No. I E21A-PS2 (I E2 IK702) 3.1.6, 3.1.31, 3.1.22 Power Supply Nominal 24.0 volts 3.2.4, 3.1.18 Power Supply Variations 23 - 28 vdc 3.2.4, 3.1.18 4.7 Instrument Tubing The CST outlet piping runs to the RCIC and HPCS pumps. One side of the transmitter is tapped into this line; the other is vented to atmosphere.

Description Data Reference Room IA201 3.1.10, 3.1.11 Normal Temp 65-1 04F 3.2.1 DBE Temp 124F 3.2.1 Vertical Rise 2.763 ft. +/-2 in. 3.1.15 4.8 Condensate Storage Tank Per 3.2.23, the normal temperature of the CST water is 130F. Per 3.2.22, this is also the maximum expected temperature (based on associated line HCD-9). During normal plant operation the minimum CST water temperature will not drop below 75F. During extended cold weather plant outages the temperature could fall below the 65F limit for the feedwater injection piping for RCIC. As a result, CST temperature monitoring instrumentation was installed. (reference 3.2.21) Procedural controls were put in place to maintain the temperature above 70F (3.2.20).

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SHEET SHEET j1Lj OF 26 CALCULATION NO. JC-OIE51-N635-1 REV. I CALCULATION BY --TV# DATE "UZfrn VERIFIED BY A1 )ATE 0Z'7 /4&.

5.0 ASSUMPTIONS 5.1 Per reference 3.1.1, the M&TE error is normally assumed to be equal to the reference accuracy of the pressure transmitter. Per reference 3.2.13, a Fluke 45

(&0.040 ma) and a pressure gage L+1.194" or +0.0995 fi) are used to calibrate IE5 1N035A & E. The total M&TE error for this device is the SRSS of the two.

Converting ma error to ft: (0.040 ma)*(40 ft / 16 ma) = 0.10 ft. The SRSS of 0.1and 0.0995 is 0.141 ft. Since this is larger than the +0.25% (40 ft) =++/-0.1 ft reference accuracy of the transmitter, the +0.141ft value will be assumed for the M&TE error.

5.2 The published 0.5% URL seismic effect for the 1153 Series B transmitters is for a 4 g peak ZPA (Ref. 3.2.6). Per reference 3.2.16, the worst ZPA experienced at Aux Building elevation 119' is 0.361g. At the 122' mounting location of the transmitters it will be conservative to assume a ZPA of 0.5g. The +0.25% URL published seismic effect for 1152 transmitters (with 3 g peak ZPA per Ref. 3.2.9) will instead be assumed because of the similarity of the sensing modules. See also reference 3.1.27 page 2-12.

5.3 Vendor documents list equipment performance data without stating the statistical basis for the numbers. Although some vendor data is "worst case", it will be assumed that all such data is a 2 sigma value.

5.4 Per reference 3.2.13 & 3.2.14, a Rosemount readout assembly is used to calibrate the Rosemount trip units. Per reference 3.2.5, the accuracy of the readout assembly is +0.01 ma which is equal to (0.01 ma)(40 ft/16 ma) = +0.025 ft and the accuracy of the trip unit is +0.2% span = 0.2% (40 ft) = +0.08 ft. However, since Ref. 3.2.13 & 3.2.14 specify a setpoint tolerance of +0.04 ma =

(0.04)(40/16) = 0.1 ft, the larger +0.1 ft value will be assumed for the M&TE error.

5.5 Assume the IR effects are negligible since the cables are not located in line break areas.

5.6 Based on data in reference 3.1.12, the trip units are currently Rosemount 510DU's. Since this model is obsolete, they may be replaced with 710DU's in the future (Ref. 3.1.25), The performance spec for the 710DU is equal or better than the 51ODU.

5.7 Assume that the standby gas treatment system maintains a 2.0 in. DP between the Aux. Building and the atmosphere outside the plant (based on PDS data for T42N03 1A/B). This will be a bias term when determining LU.

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SHEET SHEET 14 OF 26 CALCULATION NO. JC-OIE5 I-N635-I REV. I CALCULATION BY -t%.*1 DATEI/Jo6b VERIFIED BY IjO.. DATE 5.8 Per reference 3.1.27 page 2-13, and reference 3.2.12, the radiation effect is assumed to be insignificant because the accident dose is below 0.1 Mrad and dose rate is very low.

5.9 The radiation drift effect (RD) of the transmitters will be assumed to be zero since the normal dose rate is very low and the transmitters are calibrated every 18 months.

5.1 0 A RCIC flow of 825 gpm is assumed for the flow induced errors in sections 7.5, 7.7 & 7.8. Although the RCIC design flow is 800 gpm (3.1.2), the actual RCIC flow is adjustable from 0 to 1000 gpm via controller 1E51R600 (3.2.24 & 3.2.25).

References 3.2.26 & 3.2.27 specify the nominal setting for the flow controller is 800 gpm. Reference 3.2.27 specifies a flow rate acceptance criteria of 800 +10 gpm using a DVM. The assumed RCIC flow of 825 gpm (810 gpm + 15 gpm instrument uncertainty allowance) is therefore conservative.

5.11 If HPCS was also taking suction from the CST, the flow errors in sections 7.5, 7.7

& 7.8 would be much larger. However, the nominal HPCS CST setpoint is more than one foot above the calculated RCIC setpoint and the suction swap for HPCS will be completed well before the calculated RCIC setpoint. The HPCS swap will be completed between 6.115 ft and 8.844 ft per Ref. 3.2.18. For the determination of the HPCS suction swap setpoint in Ref. 3.2.18, a flow of 9000 gpm (825 gpm RCIC flow per 5.10 and a 8175 HPCS flow per Ref. 3.1.2) is assumed for the flow induced errors.

6.0 METHODOLOGY 6.1 Device Uncertainties For each module, the uncertainty terms applicable to this application will be specified and combined into the following module errors:

RA - reference accuracy L - positive bias uncertainty M - negative bias uncertainty MTE - measurement and test equipment inaccuracies D - drift

ENTERGY BCALCULATION SHEET SHEET 15 OF 26 CALCULATION NO. JC-OIE51-N635-1 REV. I CALCULATION BY "T*,* DATE "L/10.6 Iot VERIFIED BY L DATE 6.2 Loop Uncertainties The random and bias components of:

PE - errors associated with the Primary Element PM - errors in Process Measurement, and IR - errors due to degradation in Insulation Resistance will be quantified, the loop error equation given, and the device and loop uncertainties combined to produce:

AL - SRSS of all device random uncertainties except drift LL - The sum of all positive bias uncertainties ML - The sum of all negative bias uncertainties CL - SRSS of all measurement and test equipment inaccuracies used for calibration.

DL - SRSS of all drifts LU - SRSS( AL, CL, PE, PM )IR + LL - ML 6.3 Total Loop Uncertainty The total loop uncertainty will be calculated using the Ref. 3.1.1 equation:

TLU = LU + DL 6.4 Allowable Value The allowable value for the loop will be calculated using the Ref. 3.1.1 equation:

AV =AL+/-LU 6.5 Nominal Trip Setpoint The nominal trip setpoint will be calculated using the Ref. 3.1. lequation:

NTSP = AL +/- TLU 6.6 Spurious Trip Avoidance The probability of a spurious trip during normal plant operation using the Tech Spec setpoint will be evaluated using the methodology of Ref. 3.1.1 and calculated loop errors. Per Ref. 3.1.1, a 95% probability of no spurious trip is acceptable.

CALCULATION SHEET

___~ ENTERGY SHEET 1j6.. OF 26 CALCULATION NO. JC-0IE51-N635-1 REV. I CALCULATION BY "T" t? DATE -if!k§VERIFIED BY AM ) DATE O-Z. /O&

6.7 LER Avoidance The probability of exceeding the Tech Spec allowable value without a trip at the Tech Spec setpoint will be evaluated using the methodology of Ref. 3.1.1 and calculated loop errors. Per Ref. 3.1.1, a 90% probability of avoiding LERs is acceptable.

Note: When considering the probability of a spurious trip, any late actuation will be conservative. Similarly, when considering the probability of an LER, any early actuation will be conservative. This means that single sided distributions are appropriate for this evaluation.

Per Ref. 3.1.1, a Z of 1.645 corresponds to a probability of 95%. Similarly, a Z of 1.28 corresponds to a probability of 90%.

6.8 Nomenclature The nomenclature of Ref. 3.1.1, Section 1.6, will be used. Errors associated with the transmitter will be subscripted with a "1", errors associated with the trip unit will be subscripted with a "2", while loop errors will be subscripted with an "L".

For example, D1 would be the transmitter drift, D2 would be the trip unit drift, and DL would be the loop drift.

6.9 Worst Case Loop The equipment and environments for each loop are identical; therefore, no worst case calculation is required.

7.0 CALCULATION 7.1 Transmitter Uncertainties Using the vendor data from Section 4.4:

URL = 62.5 ft SPAN = 39.81 ft c 40 ft RA 1 = +/- 0.25% span

= (0.0025)*(40)

= +/- 0.100 ft Temp Effect = +/- (0.75 % URL + 0.5% span) / IOOF

= +{(0.75%)(62.5) + (0.5%)(40)}/100F

= + 0.669 ft /100F

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SHEET 17 OF 26 CALCULATION NO. JC-QIE51-N635-1 REV. 1 CALCULATION BY " L DATE folbb VERIFIED BY ]AM bATE 0 0 r.

Temperature effect will be broken into TD (65-90F per Ref. 3.1.1), TEN (90-104F, the balance of the normal range from Sec 4.2) and TEA (the additional accident range from Sec 4.2).

Therefore:

TDI = (0.669)*(25/100)

= L 0.167 ft TEN1 = (0.669)*(14/100)

+/- 0.0937 ft TEA, - (0.669)*(20/100)

-+/- 0.134 ft Per Ref. 3.2.6, humidity has no effect on the sealed transmitter.

HE, = +/- 0.00 inwc Radiation Drift (normal)

RD, = + 0.00 inwc Sec. 5.9 Radiation effect (Accident)

REA, = +/- 0.0 ft Sect 5.8 Per Sec 4.6, the worst power supply variations are -1.0 volts, +4.0 volts. For simplicity, this will be conservatively taken as +/- 4.0 volts.

PSI = +/- 0.005% span / volt variation

= +/- (0.00005)*(40 ft)*(4 volts) 0.008 ft Seismic Effects SE, = +/- 0.25% URL

= + 0.25% (62.5 ft) 0.156 ft

ENTERGY fCALCULATION SHEET SHEET 18 OF 26 CALCULATION NO. JC-0IE51-N635-I REV. I CALCULATION BY ""T*h/b'_ DATE "fs- Ic*VERIFIEDBY _*_.*DATE b &

Overpressure is a differential pressure above the upper range limit, in this case 62.5 ft. Per Ref. 3.2.11 & 3.2.8, the CST is 31 ft high, therefore, these transmitters will not experience the overpressure effect.

OVPI = 0.000 ft The static pressure effect is not applicable for gage pressure transmitters.

SPE 1 = +/- 0.00 inwc Drift is specified for six months. The actual worst case calibration period is 22.5 months (Ref. 3.1.1). Per Ref. 3.1.27page 2-8 the drift for each time interval can be combined using the SRSS methodology. Therefore:

DR, = =SQRT (22.5/6) * (0.25% URL) for 22.5 months

= +SQRT (3.75)*(0.25%)*(62.5)

= +/-0.303 ft Summarizing for the transmitter:

Al = +/- SRSS( RAI, (TENI+TEAI), REAI, PSI, SE0)

= +/- SRSS{0.100, (0.0937+0.134), 0.0, 0.008, 0.156}

+/- 0.294 ft L =+ 0.0 inwc MI =-0.0 inwc CI =+0.141 ft Assumption 5.1 Dl = SRSS(DRi, TDO)

=+/- SRSS(0.303, 0.167)

=+0.346 ft 7.2 Trip Unit Uncertainties Using the vendor values from Sec 4.5:

SPAN = 40 ft A2 = +/- 0.20% span

= +/- (0.002)* (40)

= + 0.080 ft

• CALCULATION SHEET E

ENTERG3Y CACLTO SHEETG SHEET 19 OF 26 CALCULATION NO. JC-O1E51-N635-1 REV. I CALCULATION BY V*- .". DATE"I*7?t Jo VERIFIED BY ] DATE L2 = + 0.00 inwc M2 = - 0.00 inwc C2 = +/-0.10 ft Assumption 5.4 Six months of drift allowance is included in the reference accuracy of the trip units. Since these trip units are calibrated every six months, the six month drift is equal to zero.

D2 =+0.0 ft 7.3 Primary Element Accuracy PE = + 0.00 inwc (This loop does not employ a primary element) 7.4 Process Measurement Accuracy Changes in water density caused by changes in reference leg water temperature will affect the loop accuracy by causing the transmitter to sense a level that is either lower or higher than the actual level in the CST. The PM effect associated with the density changes is determined by using the following equation extracted from reference 3.1.1 Appendix B.

PM = HV ((SVI/SV2) - 1)

The temperature in the reference leg of the transmitters will be assumed to be between 65°F to 124°F (Ref. 3.2.1) and the calibration temperature will be 90°F (Ref. 3.2.1).

HV = reference leg water height = 2.763 ft Section 4.7 SV I = specific volume at TI (90'F) = 0.016099 ft3 /lbm Ref. 3.1.28

• • Calculate PM for the lower temperature range value:

SV2 = specific volume at T2 (65°F) = 0.016041 ft3 /Ibm Ref. 3.1.28 PM tubing = (2.763)((0.016099/0.016041)-1)) = +0.001 ft

• CALCULATION SHEET

~--ENTERGY 2.

SHEET 20 OF 26 CALCULATION NO. JC-Q1E51-N635-1 REV. I CALCULATION BY -"I-%. 4 DATE 7/-"-tI10a VERIFIED BY i DATE C7/-7/ --

• • Now calculate for the upper temperature range value:

SV2 = specific volume at T2 (124°F) = 0.0 16221 ft3 /Ibm Ref. 3.1.28 PM tubing = (2.763)((0.016099/0.01622 1)-1)) = -0.021 ft PM tubing = + 0.001 ft, -0.021 ft Changes in the CST water temperature will result in level changes that are not detected by the level transmitters. The PM effect associated with the density changes is again determined by using the following equation extracted from reference 3.1.1 Appendix B.

PM = HV ((SVI/SV2)- 1)

The worst case PM error would be at the 30.167 ft high alarm setpoint (3.2.17).

However, for this calculation it is only necessary to consider the error at the 5.083 ft low level setpoint (3.2.8).

HV = CST water level = 5.083 ft SVI = specific volume at TI (130'F) = 0.01625 ft3 /lbm Ref. 3.1.28 SV2 = specific volume at T2 (70°F) = 0.01605 ft3 /Ibm Ref. 3.1.28 PM CST = (5.083)((0.01625/0.01605)-1)) = +0.063 ft PM total = SRSS (PM tubing, PM CST)

= +SRSS(0.001, 0.063), -SRSS(0.021, 0.00)

= +0.063, -0.021 Assume PM = +0.063 ft 7.5 Friction Loss Bias For an ideal CST level measurement, the transmitter would have a dedicated sensing line with a tap near the bottom of the tank like the non-safety related CST level transmitter I P11N003. This transmitter is located inside the CST dike area near the CST. Bechtel chose to locate the safety related CST level transmitters

CALCULATION SHEET ENTERGY SHEET 21 OF 26i CALCULATION NO. J- IE I-N6 --1 REV. I CALCULATION BY DATE 1'1 66VERIFIED BY M DATE inside the Aux Building so that they would not have to design a means of protecting them from seismic and tornado missel hazards. Instead of providing a dedicated sensing line to the transmitters in the aux building, Bechtel chose to utilize a tap off of the 20" HCB-9 HPCS / RCIC suction line. With zero flow, the level readings of the safety related level transmitters will be correct. With flow, the measured pressure will be less than the CST pressure due to frictional pressure drops in the pipe. This will result in a lower level being indicated (Ref.

3.1.19). Per Ref. 3.2.2 Att 5 page 4, the friction loss error is 0.017 ft at 500 gpm, 0.044 ft at 825 gpm and 0.063 ft at 1000 gpm.

FL = -0.044 ft Assumption 5.10 7.6 Ventilation System Bias NRC information notice IEN 97-0033 was issued to advise addressees of the potential adverse affects ventilation systems can have on level instrumentation (Ref. 3.1.24). The level transmitters of this calculation have low pressure ports opened to the ambient pressure of area 1A201 of the Aux. Building. The fuel pool area ventilation system maintains the Aux. Building at a negative pressure. This causes the level transmitters to indicate the CST level 0.7 inwc higher than it actually is based on PDS data for T42N037A/B. When the Standby Gas Treatment system is operating, the indication of the CST level by the transmitters could be 2.0 inwc (0.167 ft) higher than it actually is based on the PDS data for T42N037A/B.

VNT= +0.167 ft (Ref. 4.9) 7.7 Response Time (Drawdown) Bias The suction swap to the suppression pool will be delayed because of instrument response times and valve stroke times. As a result, the level of the CST will drop below the low level trip setpoint. Per Ref. 3.2.2, the maximum "drawdown" effect is 0.047 ft at 500 gpm, 0.078 ft at 825 gpm and 0.094 ft at 1000 gpm. The minimum "drawdown" effect is 0.0046 ft at 500 gpm, 0.076 ft at 825 gpm and 0.092 ft at 1000 gpm.

RTmax = +0.078 ft Assumption 5.10

_..* ENTrERGY GCALCULATION

/ '. :

SHEET SHEET 22 OF 26 CALCULATION NO. JC-01E51-N635-1 REV. I CALCULATION BY 21'_ L. DATE 1 ý:.IOg VERIFIED BY M DATE 07 c*

7.8 Vortexing Per Ref. 3.2.2 Sht 35, vortexing could occur at -0.319 ft indicated level at a flow rate of 500 gpm, -0.295 ft at 825 gpm flow and -0.277 ft at 1000 gpm. Since the level that vortexing will occur is well below the 4.0 ft low level setpoint, vortexing is not a concern with RCIC.

VTX = +0.0 ft Assumption 5.10 7.9 Effective Flow Induced Error The total Effective Flow Induced Error is the sum of the Friction loss, Response Time and Vortexing errors.

FlEmax = FL + RTmax + VTX

= -0.044 + 0.078 + 0.0

= +0.034 ft FlEmin = FL + RTmin + VTX

= -0.044 + 0.076 + 0.0

= +0.032 ft 7.10 Insulation Resistance Bias IR = +0.0 Assumption 5.5 7.11 Loop Uncertainties Using the equations from Ref. 3.1.1 and the values from above:

AL =+SRSS( Al, A 2)

= + SRSS( 0.294, 0.080)

-+0.305 ft LL = + L, + L2 = 0.0 inwc ML = MI - M 2 =0.0 inwc CL = + SRSS(Ch, C 2)

-- SRSS(0.141, 0.10)

-+0.173 ft

• CALCULATION SHEET ENTERGY SHEET 23 OF 26 CALCULATIONNO. JC-0E5 -N635-1 REV. I CALCULATION BYV"* ... DATE JIk'IL*b VERIFIED BY E DATE 0TZ47 DL =+/- SRSS(DI, D2)

- +/- SRSS(0.346, 0.0)

- 0.346 ft LU+ + SRSS(AL, CL, PM, PE) + IR + VNT + VTX + RT max

= + SRSS( 0.305, 0.173, 0.063, 0.0) + 0.0 + 0.167 + 0.0 + 0.078

= + 0.356 + 0.245

= +0.601 ft LU. = - SRSS( AL, CL, PM, PE) + FL

= - SRSS( 0.305, 0.173, 0.063, 0.0) - 0.044

= -0.400 For comparison, the loop uncertainties LU'+: LU'. without the FIE error will be calculated.

LU'+ = + SRSS( AL, CL, PM, PE ) + IR + VNT

= + SRSS( 0.305, 0.173, 0.063, 0.0) + 0.0 + 0.167

= + 0:356 + 0.167

= +0.523 ft LU'. = - SRSS( AL, CL, PM, PE)

= - SRSS( 0.305, 0.173, 0.063, 0.0)

= -0.356 ft 7.12 Total Loop Uncertainty TLU+ = LU+ + DL

- + 0.601 + 0.346

= + 0.947 ft TLU. = LU. - DL

= - 0.400 - 0.346

-- 0.746 ft Without FIE error; TLU'+ = + SRSS( AL, CL, DL PM ) + VNT

= + SRSS( 0.305, 0.173, 0.346, 0.063) + 0.167

= + 0.497 + 0.167

= +0.664 ft

ALCULATION SHEET ENTERGY C, SHEET 24 OF 26 CALCULATION NO. JC-OIE5I-N635-1 DATE R

,CALCULATION BY _:nth DATE 7k0 VERIFIED BY TLU'. = - SRSS( AL, CL, DL, PM)

= - SRSS( 0.305, 0.173, 0.346, 0.063)

-- 0.497 ft 7.13 Allowable Value AV = AL + LU+

= 3.0 + 0.601

= 3.601 ft I The specified allowable value will be 3.7 ft.

7.14 Nominal Trip Setpoint NTSP = AL + TLU+

- 3.0 + 0.947

= 3.947 ft I The specified setpoint will be 4.0 ft.

The minimum CST level after the RCIC suction swap Lmin = NTSP - TLU'+

- FIE max = 4 - 0.664 -0.034 = 3.302 ft at 825 gpm. The maximum CST level after the RCIC suction swap, Lmax = NTSP - TLU'. - FIE min = 4 - (-0.497) -

0.032 = 4.465 ft at 825 gpm.

7.15 Spurious Trip Avoidance Sigmaj = (1/n)

• SRSS( LU+, DL) Ref. 3.1.1 n=2 Sec 5.3 Sigmai = (1/2)

• SRSS( 0.601, 0.346)

= 0.347 I It is assumed that the minimum normal operating value of the CST would be equivalent to the CST low level alarm (I P 1I K603) of 23'-1" actual or 22'-0" indicated (Ref. 3.2.17).

XT = 22.0 ft

_ENTERGY fCALCULATION SHEET SHEET 25 OF 26 CALCULATION NO. $¢- IE5 -N635-] REV. I CALCULATION BY "-"& DATE" /l3T c. VERIFIED BY ff [&DATE t27 SigmaN is the standard deviation associated with XT. In this application, XT is assigned as a enveloping value and SigmaN should be set to zero.

SigmaN = 0.00 Z = ABS(Tech Spec SP - XT) / SRSS(SigmaN, Sigmaj) Ref. 3.1.1

= ABS(4.0 - 22.0) / SRSS(O.00, 0.347)

= 51.873 This is above the Sec 6.6 minimum acceptable Z value of 1.65 for 95%.

7.16 LER Avoidance Sigma, (1/n)

• SRSS ( AL, CL, DL) n =2 Sigma, = (1/2)

• SRSS (0.305, 0.173, 0.346)

= 0.246 Z - ABS(Tech Spec AV - Tech Spec SP) / Sigma, Ref. 3.1.1

= ABS(3.7 - 4.0) / 0.246

= 1.220 This is slightly below the Sec 6.7 minimum acceptable Z value of 1.28 for 90%.

However, the LER avoidance evaluation does not require the inclusion of accident or seismic effects. A new sigma' without these uncertainties will be derived and the associated Z' will be calculated.

A'l =+SRSS( RAI, TENI, PSI)

= + SRSS{0.100, 0.0937, 0.008}

=+/-0.137ft A' 2 =A 2 ==+0.080 ft A'L = + SRSS( A'1 , A' 2)

= SRSS( 0.137, 0.080)

= + 0.159 ft Sigma'i = (1/2)

• SRSS ( A'L, CL, DL)

= (1/2)

• SRSS(0.159, 0.173, 0.346)

= 0.209

CALCULATION SHEET I - ENTERGY SHEET 26 OF 26 CALCULATION NO. JC-QI E5 I-N635-I REV._I ,

CALCULATION BY "fl,\S* DATE 10b VERIFIED BY ] /DATE iZ06

=ý ABS(Tech Spec AV - Tech Spec SP) / gigm~a'i

= ABS(3.7 - 4.0) / 0.209

= 1.435 This is above the Sec 6.7 minimum acceptable Z value of 1.28 for 90%.

8.0 CONCLUSION

The Tech Spec setpoints and allowable values support the safety function (are conservative with respect to the calculated values) and give adequate margin from spurious trips and LERs. Therefore, they are acceptable. The minimum CST level after the RCIC suction swap is 3.302 ft at 825 gpm. The maximum CST level after the RCIC suction swap is 4.465 ft at 825 gpm. I

SUMMARY

OF RESULTS SYSTEM E51 LOOP NUMBERS N635A & E TOTAL LOOP UNCERTAINTY + 0.947, - 0.746 ft LOOP UNCERTAINTY + 0.601, - 0.400 ft DRIFT ALLOWANCE +/- 0.346 ft M&TE +/- 0.173 ft SPECIFIED (ft) CALCULATED (ft)

Analytical Limit 3.0 Allowable Value Nominal Trip Setpoint 3.7 (TS) 4.0 (TRM) 3.601 3.947 I