JAFP-10-0033, Attachment 2 to JAFP-10-0033, Calculation JAF-CALC-NBS-02052, Revision 4

Attachment 2 to JAFP-10-0033, Calculation JAF-CALC-NBS-02052, Revision 4

ML100750523
Person / Time
Site:	FitzPatrick
Issue date:	03/05/2010
From:	Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation
References
JAFP-10-0033, TAC ME1819 JAF-CALC-NBS-02052, Rev 4
Download: ML100750523 (35)

Text

JAFP-1 0-0033 Attachment 2 Calculation JAF-CALC-NBS-02052, Revision 4 (34 Pages)

ATTACHMENT 9.2 ENGINEERING CALCULATION COVER PAGE Sheet 1 of 2

[] ANO-1 17 ANO-2 LI GGNS El IP-2 El IP-3 [] PLP Z JAF ErPNPS El RBS El VY El W3 LI NP-GGNS-3 El NP-RBS-3 CALCULATION EC # 13686 Page 1 of 34 COVER PAGE Design Basis Calc. E YES E-- NO H CALCULATION E- EC Markup Calculation No: JAF-CALC-NBS-02052 Revision: 4

Title:

Setpoint Calculation for Rx High Pressure SDC Editorial:

Isolation Function (02-3PT-55A,D and 02-3STU-251 A, D) EI YES E NO System(s): 02-3 and 10 Review Org (Department): Design I&C Safety Class: Component/Equipment/Structure Type/Number:

Ej Safety I Quality Related 02-3PT-55A 02-3PT-55D F] Augmented Quality Program F[ Non-Safety Related 02-3MTU-255A 02-3MTU-255D 02-3STU-251 A 02-3STU-251 D Document Type: Engineering Calculation Keywords (Description/Topical Codes):

None REVIEWS Name/Signature/Date Name/Signature/Date Name/Signature/Date A, Yost / See IAS A. Lilienthal / See [AS See IAS Responsible Engineer E- Design Verifier Supervisor/Approval E] Reviewer

-ElComments Attached El Comments Attached EN-DC-126 REV 3

ATTACHMENT 9.3 CALCULATION REFERENCE SHEET CALCULATION CALCULATION NO: JAF-CALC-NBS-02052 REFERENCE SHEET R

REVISION: 4 I. EC Markups Incorporated (N/A to NP calculations)

1. None.

2.

3.

4.

5. _ _ _ _ __ _ _ _

i1. Relationships: Sht Rev Input Output Impact Tracking Doc Doc Y/N No.

1. See calculation details 0 0 2.

3.

4.

o0 0][

0 0

5. o 0 _ _

Ill. CROSS

REFERENCES:

1. None

2. "

4.

IV. SOFTWARE USED:

e: None Version/Release: Disk/CD No.

V. DISK/CDS INCLUDED:

Title:

None Version/Release Disk/CD No.

VI. OTHER CHANGES:

None EN-DC-126 REV 3

ATTACHMENT 9.4 RECORD OF REVISION Sheet 1 of 1 Revision Record of Revio-See Section 1.1.1 for Record of Revisions EN-DC-126 REV 3

CALCULATION SHEET TABLE OF CONTENTS SECTION PAGE

1. OBJECTIVE/ DESIGN BASIS ............................................................................................ 6

2. UNVERIFIED ASSUMPTIONS ............................................ 10....

3. AFFECTED COMPONENTS .............................................................................................. 11

4. REFERENCES ...................................................................................................................... 13

5. DATA COLLECTION .............................................................. ......................... 16

6. CALCULATIONS .................................................................................................................. 18

7. SCALING .............................................................................................................................. 30

8. CONCLUSIONS ..................................................................................................................... 32

CALCULATION SHEET List of Effective Pages Revision 4 All pages Revision 3 Pages 1,2,3,5,6,8,12,13,17,19,20,21,22,25,26,27 Revision 2 All remaining pages

OBJECTIVE/ DESIGN BASIS 1.1. Objective 1.1.1. Reason for the Calculation and the revision This calculation determines the instrument channel uncertainties associated with the Reactor High Pressure Shutdown Cooling Permissive trip loop and establishes the Limiting Trip Setpoint (LTS),

Allowable Value (AV) and calibration tolerances for this function.

Revision 1 has been developed to determine the Allowable Value (AV) for the new Improved Technical Specifications (ITS), Open Item 204, based on the Analytical Limit (AL) provided in Ref. 4.2.18.

Revision 2 of this calculation provides a calculated lower allowable value (CAVE) based on the provided lower EAL. ACTS 02-63485 determined AV's will be provided in the TRM. Rev.1 of this calculation does not establish both upper and lower AV's for the CTS Table 3.2-2 being relocated to the TRM. This Calculation revision is necessary to provide a lower AV for the TRM using the lCD since one wasn't previously provided. Revision 1 was an Interim status calculation for ITS implementation. Revision 2 is a Pending status calculation.

Revision 3 of this calculation is a limited revision. With this revision, ER [[::JAF-04-10283|JAF-04-10283]] will be resolved by raising the Field Trip setting closer to the Upper Limiting Trip setpoint. This is done by taking advantage of existing margin between the existing Field Trip Setpoint (FTS) of 62 psig and the Upper Limiting Trip Setpoint (LTSu). The setpoint change is required to support application of noble metals and will help minimize isolation of SDC during normal initiation of SDC.

Normally SDC is run at 0 psig reactor pressure. Injection of Noble metals requires the Reactor to be at 25 to 30 psig. Past experience shows that isolations have occurred with the 62 psig setpoint. It is believed that water hammer due to less than adequate venting of the SDC lines may have contributed to SDC isolation initiation. Improved venting techniques have been put in place. Raising the setpoint will reduce the likelihood of getting an isolation of SDC during noble metals application and plant outage conditions. The Field Trip Setpoint will be raised as appropriate without challenging the existing Technical Specification Upper Allowable Value of < 74 psig. This is processed as a Limited Revision due to the impact of the change in setpoint value on the computation of Temperature error (TE 1 ) and the resulting impact on Channel Uncertainty.

Revision 4 of this calculation reflects the installation of EC 13686. With EC1 3686, the SDC isolation function was removed from the pressure switches 02PS-128A, B. The pressure switches were removedfrom the plant and the process lines and circuit cable spared in place. The SDC isolation function is now provided by the ATTS transmitters 02-3PT-55A, D and slave trip units 02-3STU-251A, D. The SDC isolation function was removed from 02PS-1:28A, B because the switches sense reactor pressure at the "B" reactor water recirculation piping where they were susceptible to hydraulic pressure transients and SDC would inadvertently isolate. With the ATTS transmitters and trip units providing the SDC isolation function, it is possible to sense reactor pressure at a location that is not susceptible to hydraulic transients while maintaining the design function of the circuit.

This calculation supersedes JAF-CALC-NBS-02052 Rev. 3.

1.1.2. Method for achieving objectives The calculation is developed in accordance with EN-DC-126 (Ref.

4.2.2) following the guidance and methods provided in ENN-IC-G-003 (Ref. 4.2.1).

1.2. DESIGN BASES/ASSUMPTIONS Not Requiring Verification 1.2.1. In accordance with ENN-IC-G-003, Reference 4.2.1, this function is a Type 2 setpoint and Rigor R2.

1.2.2. The existing transmitter as-left tolerance in the calibration procedures (Ref. 4.2.4.1 and 4.2.4.2) is given as +/- 0.01 Vdc (+

0.25%) and represents the vendor specified accuracy. This calibration acceptance criteria satisfies the guidance in ENN-IC-G-003 and will not be changed.

1.2.3. It is assumed that the effects of normal radiation are calibrated out on a periodic basis. Outside Containment, there is not a substantial increase in radiation during normal operation. For this reason, the uncertainty introduced by radiation effects is assumed to be negligible.

1.2.4. Typically manufacturers' literature and technical manuals do not address Humidity Effects (10% RH to 95%RH) on their equipment. The uncertainty introduced by humidity changes during normal operation is assumed to be negligible unless the manufacturer specifically discusses humidity effects. The effects of humidity changes are assumed to be calibrated out on a periodic basis. A condensing environment is considered an abnormal event that would require equipment maintenance.

Humidity levels below -10% are considered to occur very infrequently.

1.2.5. Seismic uncertainty effects are not included in this calculation based on the following: Per Reference 4.2.11, this instrument loop's functions are not required during and following a seismic event. They are, however, required to be operable before a seismic event. Should a seismic event occur, operability will be evaluated per Reference 4.2.13.

.1.2.6. EN-DC-210 (Ref 4.2.14), Attachment 9.5, item 02g identifies the low pressure signal during RHR SDC mode to close 10MOV-25A, B as categorized with a short operating time. The expected operating time is listed as 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. JAF-ICD-RHR-03174 (Ref.

4.2.18) provides the equivalent analytical limits associated with the SDC isolation logic. Review of ref 4.2.18 identified this function is not credited in any accident analysis. DBD-010 (Ref 4.2.11) identifies the SDC isolation function as not having any accident mitigating functions. Considering the above, this function is not required to mitigate the consequences of an accident and thus instrument errors due to harsh environmental effects including process measurement and IRE do not need to be considered.

1.2.7. Generally the temperature at which an instrument is calibrated is within the normal operating range of the instrument. Also, any ambient temperature effects are typically small. Therefore, the uncertainty associated with the temperature variations during calibration is assumed to be negligible. This assumption applies only to temperature changes during calibration. Temperature effects over the expected range of equipment operation from the calibration temperature still must be considered.

1.2.8. For M&TE devices, it is assumed that the standard used in calibration of the M&TE has an accuracy which is 4 times better than the accuracy of the calibrated M&TE as per the requirement stated in Section 5.7.1 of the M&TE program (Ref. 4.2.5).

CALCULATION SHEET 1.2.9. This calculation has been completed for one Reactor High Pressure Shutdown Cooling isolation logic instrument loop (02-3PT-55A). Because the instrument configuration of the 02-3PT-55D loop is identical, the computed uncertainties and setpoint is applicable to both instrument loops. Due to the different elevations that 02-3PT-55A and 02-3PT-55D are installed, each transmitter has a different static head correction included into the calibration (Ref. 4.2.6 and 4.2.7). Static head correction is not an input for development of instrument uncertainty.

1.2.10. Temperature, humidity, and radiation levels in the relay room for the ATTS cabinets are assumed to be normal. The Rosemount MTUs and STUs are located in the ATTS, a controlled environmental area, such that the normal operating conditions and accident conditions for vendor specified accuracy, calibration, and setting tolerance are the same. Therefore, for the purposes of this calculation, the random error for normal and accident conditions are the same for the trip units.

1.2.11. Rosemount Model Trip Units 51ODU and 710DU are interchangeable, and this calculation encompasses the use of either model. During accident conditions the two models have different specifications and the worst case specification will be used to insure interchangeability. However, for this calculation, the trip units are located in the relay room for which the normal conditions exist during accident environment as per Section 1.2.10.

1.3. LOOP FUNCTION The transmitters 02-3PT-55A, D monitor reactor steam dome pressure.

The transmitters send a signal through Master Trip Units to the bistable units 02-3STU-251A, D which actuate the primary relays 05A-K109A, D.

The Shutdown cooling isolations occur when either 05A-K109A or 05A-K109D contacts actuate due to high reactor pressure. The purpose of this logic is to close 1OMOV-17 and 1OMOV-18 which prevents the over pressurization of the RHR pump suction piping.

When the reactor pressure is equal to or less than the SDC cut-in pressure, a reactor low pressure signal is generated. The low-pressure signal is sent to the RHR injection valve control circuit for processing the injection valve (10MOV-25A, B) isolation signal. The low-pressure signal is also sent, via the Primary Containment Isolation System, to permit opening of SDC isolation valves 10MOV-1 7, 18 during the SDC mode. When the reactor pressure is above the SDC cut-in pressure, the pressure switches generate a reactor high-pressure signal to close the SDC isolation valves (Section 3.7.15.1 of Ref. 4.2.11 and Ref.

4.2.15).

2. UNVERIFIED ASSUMPTIONS None

CALCULATION SHEET

3. AFFECTED COMPONENTS 3.1. LOOP (BLOCK) DIAGRAM Figure 1 Relay Room Elevation 284' 8" Reactor Building Panel 09-91 MTU

)2-3MTU-255A (Reactor Auto Scram rrip Logic Al)

Not addressed with this calculation - see JAF-CALC-NBI-00192 Notes: The D Loop is identical. The B and C loops do not include SDC isolation logic.

Page No: Total pages:

CALCULATION SHEET 12 34 Calculation Number: JAF-CALC-NBS-02052 Revisi 4

No:

3.2. Environmental Table 1 Environmental Table Nodes Location Event Humidity Radiation Temp Ref.

(R.H.) (TID)( R) ('F) 02-3PT-55A,D Reactor Normal 20-90% 1.8x10 4 85- 100 4*2.3 (RB300SWITCH, Building (40 yrs) 4.2.14 RB300NORTH) Elev 300' LOCA Same as Same as Same as 1.2.6 Normal Normal Normal HELB Same as Same as Same as 1.2.6 Normal Normal Normal I ATTS Relay Room, Normal 40-50% 1.75x10W 60-90 4.3.2.1 Elev 284', 8" (40 years) 4.3.2.2 4.2.22 LOCA/ Same as Same as Same as I HELB Normal Normal Normal 3.3. Instrumentation Table 2 Instrumentation Table (Reference 4.2.17)

Component ID Function Manuf/ Rack/id Environmental Model No. Cabinet Zone 02-3PT-55A, D Reactor High Rosemount 25-05/25-06 Reactor Building, Pressure Scram 1153GB9RC Elevation 300'

/ SDC Isolation 02-3MTU-255A, D Rx High Press Rosemount 09-91, 94 ATTS Scram 510 DU Elevation 284' 8" 02-3STU-251 A, D Reactor High Rosemount 09-91, 94 ATTS Press SDC 710 DU Elevation 284' 8" Isolation

4. REFERENCES 4.1. General None 4.2. JAFNPP Documents 4.2.1. ENN-IC-G-003, Rev. 0 - Instrument Loop Accuracy and Setpoint Calculation Methodology 4.2.2. EN-DC-126, Rev. 2 - Calculations 4.2.3. JAF-RPT-MISC-04046, Rev. 0 - Environmental Qualification Service Conditions 4.2.4. Instrument Surveillance Procedures:

4.2.4.1. ISP-200A, Rev.18 - RPS-PCIS (Al CHANNEL)

Pressure Transmitter Calibration (ATTS)**

4.2.4.2. ISP-200D, Rev.19 - RPS-PCIS (B2 CHANNEL)

Pressure Transmitter Calibration (ATTS)**

4.2.4.3. ISP-10OA-RPS, Rev. 33 - RPS INSTRUMENT FUNCTIONAL TEST\CALIBRATION (ATTS)**

4.2.4.4. ISP-i0OD-RPS, Rev. 34 - RPS INSTRUMENT FUNCTIONAL TEST\CALIBRATION (ATTS)**

4.2.5. EN-MA-105, Rev. 3 - Control of Measuring and Test Equipment.

4.2.6. JAF-CALC-NBI-00685, Rev.0 - Static Head Correction for02-3PT-55A and 02-3PT-55B.

4.2.7. JAF-CALC-NBI-00686, Rev. 0 - Static Head Correction for 02-3PT-55C and 02-3PT-55D.

4.2.8. JAFNPP, Final Safety Analysis Report 4.2.9. JAF-RPT-RPS-00456, Rev. 1 - Instrument Drift Analysis for RPS Report. Table 3, pg. 23.

4.2.10. JAFNPP, Improved Technical Specifications (ITS) and Bases, Table 3.3.6.1-1 and bases 3.3.6.1, Item 6a.

4.2.11. DBD-010, Rev. 12 - Design Basis Document for Residual Heat Removal System 4.2.12. USI-A-46, Rev. 5 - JAFNPP Safe Shutdown Equipment and Relay Evaluation.

4.2.13. AOP-14, Rev.12 - Earthquake.

CALCULATION SHEET 4.2.14. EN-DC-21 0, Rev. 1, Environmental Qualification Master List Control 4.2.15. Drawings:

4.2.15.1. FM-26A, Rev.52 - FLOW DIAGRAM REACTOR WATER RECIRCULATION SYSTEM 02-2 4.2.15.2. 1.65-129, Rev. 10 - ELEMENTARY DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM.

4.2.15.3. 1.65-130, Rev. 11 - ELEMENTARY DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM RELAY LOGIC CIRCUIT B SH. 7.

4.2.15.4. 1.70-110, Rev. 8 - ELEMENTARY DIAGRAM PRIMARY CONTAINMENT ISOLATION SYSTEM.

4.2.15.5. FM-47A, Rev. 48 - FLOW DIAGRAM NUCLEAR BOILER VESSEL INSTRUMENTS SYSTEM 02-3 4.2.15.6. 1.60-15, Rev. 5 - ELEMENTARY DIAGRAM RPS AND ECCS ANALOG TRIP SYSTEM 4.2.15.7. 1.60-16, Rev. 12 - ELEMENTARY DIAGRAM ANALOG TRIP SYSTEM ATTS.

4.2.15.8. 1.60-18, Rev. 6 - ELEMENTARY DIAGRAM ANALOG TRIP SYSTEM ATTS 4.2.15.9. 1.60-22, Rev. 12 - ELEMENTARY DIAGRAM ANALOG TRIP SYSTEM ATTS 4.2.15.10.1.60-25, Rev. 10- ELEMENTARY DIAGRAM ANALOG TRIP SYSTEM ATTS 4.2.15.11.LP-02-3N, Rev. 1 - LOOP DIAGRAM NUCLEAR BOILER INSTRUMENTATION REACTOR VESSEL HIGH PRESSURE AUTO SCRAM Al 02-3PT-55A SYSTEM 02-3 4.2.15.12.LP-02-3R, Rev. 1 - LOOP DIAGRAM NUCLEAR BOILER INSTRUMENTATION REACTOR VESSEL HIGH PRESSURE AUTO PRESSURE B2 02-3PT-55D SYSTEM 02-3 4.2.16. ETR 2062.1, Rev. 2 - Ecotech Study for NYPA, "General Analysis of cable circuitry performance at JAFNPP", issued 3/13/90 (EQ Ref. 371).

4.2.17. Asset Suite EDB, JAFNPP

Page No: I Total pages:

CALCULATION SHEET 15 34 Calculation Number: JAF-CALC-NBS-02052 Revision No:

4 4.2.18. JAF-ICD-RHR-03174, Rev. 1 and associated EC 13686 markup -

Analytical Limit for RHR Shutdown Cooling Isolation.

4.2.19. Technical Requirements Manual, Section 3.3.A, Bases Section B3.3.A 4.2.20. ER [[::JAF-04-10283|JAF-04-10283]], Raise the Field Trip Setting (FTS) to be closer to upper Limiting Trip Setpoint (LTS) [Historical reference]

4.2.21. JAF-CALC-MISC-03364, Rev. 0 - Rosemount Digital Readout Assembly - Test Equipment Total Uncertainty 4.2.22. DBD-070, Rev. 13 - Design Basis Document for Control Room and Relay Room Ventilation and Cooling Systems 4.3. Vendor Documents 4.3.1. R369-0030, (Binder R08), Rosemount Model 1153 Series B Pressure Transmitters for Nuclear Service, Publication No. 4302, 1991.J 4.3.2. MTU Vendor Manuals 4.3.2.1. R369-0029, (Binder R08), Rosemount Model 710 DU Trip/Calibration System Instruction Manual 4471 -1, Rev. A, 1983. Page 3, Tables 5, 7, 8.

4.3.2.2. R369-0032, (Binder R08), Rosemount Model 510 DU Trip/Calibration System Instruction Manual 4247-1, 1976. Page 4, Tables 5, 6, 7, 8, Figure 13.

4.4. Attachments None

CALCULATION SHEET

5. DATA COLLECTION 5.1. Input Data TABLE 3 INPUT TABLE Component ID Designator Value Ref Comments EAL (upper) 75 psig 42.18 EAL (lower) >40 psig 4.2.18 Transmitters Input 14 - 1214 psig (A) 4.2.4.1 Rosemount Transmitter -

02-3PT-55A,D 13 - 1213 psig (D) 4.2.4.2 Identical in each loop. The 4.2.6 input range accounts for a 4.2.7 positive bias static head.

pressure.

Output 1 - 5 Vdc 4.3.1 4 Vdc span over 1500 psig 4 - 20 mADC range MED 30 +/- 0.45% URL 4.2.9 30 Month Drift Value RA, + 0.25%Span 4.3.1 Reference Accuracy TE, + (0.75%URL+0.5% 4.3.1 For a temperature range of 0 40°F to 200OF Span)/100 F RE 1 + 4% URL after 4.3.1 2.2x10 7 rads TID DR, + 0.2% URLU30 months 4.3.1 URL = 3000 psig SE, N/A 4.3.1 The Seismic effect is specified as +/- 0.5% URL, but not considered in this calculation as per Section 1.2.5.

HE, N/A 4.3.1 For humidity of 0- 100%, HE, is bounded by the RA term.

SP, N/A 4.3.1 There is no static pressure effect specified.

OP 1 N/A 4.3.1 Maximum zero shift after 4500 psi: +/- 0.5% URL. The Transmitters are not overranged. Therefore,

__Overpressure effect is ,ero.

PS 1 < 0.005% Nolt 4.3.1 Assumed as % of span Transmitters MTEH + 0.05% (RANGE) 4.2.4.1 Heise Gauge (0 - 2000 psig) 02-3PT-55A, D .4.2.4.2 or equivalent MTEOMM +/- 0.05% of Reading + 4.2.4.1 Digital Multimeter (DMM),

2 Digits 4.2.4.2 Fluke 8060A or equivalent MTERES +/- 0.05% Reading 4.3.1, 250Q resistor

_figure 13 ALT, + 0.25% Span Section _ 0.01 VDC. For a span of 1-5 1.2.2 VDC, this is equal to +/-

b x /4 = + 0.25 % Span.

00.0x

CALCULATION SHEET TABLE 3 INPUT TABLE Component ID Designator Value Ref Comments 02-3MTU-255A, D Input 4-20 mADC 4.2.4.3 (4-20 mADC) = 14 - 1214 psig 02-3STU-251A, D 4.2.4.4 or 13-1213 psig 1200 psig/16mADC MTE 2 + 0.17 % Span 4.2.21 Readout Assembly Resolution (0.01 mA)

RA 2A + 0.15% span (MTU) 4.3.2 MTU analog output to slave ALT 2A + 0.1875% Span +/- 0.03 mADC Calibration Tolerance (0.03 mADC/16 mADC) xl00 = 0.1875 RA 3 T + 0.20% span (STU) 4.3.2 (Normal Cond/Normal Env)

Trip point repeatability requirements listed are valid for up to six months of operation. Normal Cond/Normal Env value is taken as setpoint accuracy ALT 3T +/- 0.2% Span 4.2.1 5.2. M&TE Table 4 Make/Model Range of Accuracy for Used to Comments Scale(s) Scale Calibrate Heise Gauge 0 - 2000 +/- 0.05 % of 02-3PT-55 (or equivalent) psig Full Scale A,D Fluke/8060A 20 Vdc +/- 0.05% Reading + DMM (or equivalent) 2 Digits resolution is taken as 0.001 Vdc.

Digital Readout 16 mA +/- 0.17 % Span 02-3MTU -

Assembly 255 A,D /

02-3STU-1 251A, D

Page No: Total pages:

CALCULATION SHEET 18 34 Calculation Number: JAF-CALC-NBS-02052 Revision No:

4

6. CALCULATIONS INSTRUMENT CHANNEL UNCERTAINTY (CU)

Per Reference 4.2.1, the instrument channel uncertainty can be calculated with a single loop equation containing all potential uncertainty values, or by a series of related term equations. The specific channel calculation will coincide with the channel's layout from process measurement to final output module or modules. Random channel uncertainties may be combined using Square-Root Sum-of-Squares (SRSS) method. Any positive (B÷) or negative (B) bias associated with the instrument channel uncertainty is combined algebraically.

The typical equation for linear CU will have the following form.

CU =+PM2 + PE2 + (e,,)2 + (eR)2 + .... +(eR)2 + B+/- + IRE Where:

PM = Random uncertainties that exist in the channel's basic Process Measurement.

PE = Random uncertainties that exist in the channels Primary Element or; any system element that quantitatively converts the measured variable energy into a form suitable for measurement.

B+/- = A sum total of all the bias components of the individual components and uncertainty of the process that consistently has the same algebraic sign and is expressed as an estimated limit of error.

IRE = Insulation Resistance Effect leakage allowance in %

of span; resulting from high humidity and temperature subsequent to an accident.

eR = Random uncertainties that are associated with any module or; assembly of interconnected components that constitutes an identifiable device, instrument, or piece of equipment.

CALCULATION SHEET 6.1. Process Measurement Effects The process measurement uncertainties associated with this application are primarily attributable to the density changes in the process fluid.

Calculations JAF-CALC-NBI-00685 and JAF-CALC-NBI-00686 determined a static head correction for 02-3PT-55A, D assuming process line pressure of 1000 psi and drywell temperature of 137.2 deg F. The static head correction factor was incorporated into the ISPs (Ref. 4.2.4.1 and 4.2.4.2). The change in process line fluid density from normal plant operating conditions to plant shutdown conditions will have a negligible effect on the considered static head pressure. This calculation assumes that any additional uncertainty attributable to normal changes in reactor conditions will have a negligible effect on the overall channel uncertainty.

By changing the location of the function of 02PS-128A, B to the ATTS instruments 02-3PT-55A, D, the sensing location will change from an elevation that matches the RHR piping to one that is approximately 30 feet higher. The new sensing location at Reactor Building elevation 300' will impart an additional static head pressure of approximately 35 psig on the RHR piping at elevation 252'. This static head pressure in addition to the 75 psig upper analytical limit is well within the RHR piping design pressure of 195 psig at 350 deg F. This ensures that the calculated setpoints will be low enough to protect the system equipment from overpressurization.

As processed with Revision 3 of this calculation, a higher setpoint is desirable from a plant operations perspective since SDC will be available for a greater range of reactor pressure.

Therefore:

PM = 0 6.1.1. Primary Element Effect (PE)

There is no primary element in this configuration; therefore, PE =0 6.1.2. Insulation Resistance Error (IRE 1 )

Per Section 1.2.6, there are no harsh environment effects on this instrument loop. Since IRE is an error mainly associated with harsh environments, this effect is not applicable. In addition, IRE is a positive bias. Development of setpoints associated with an increasing process does not consider positive biases. Therefore:

IRE=0

CALCULATION SHEET 6.2. Instrument Module Uncertainties 6.2.1. Pressure Transmitter Uncertainty (el) 6.2.1.1. Reference Accuracy (RA 1 )

Using drift binding number, RA 1 is included in MED30 term, per Ref. 4.2.1.

6.2.1.2. Drift (DR,)

From Ref. 4.2.9, MED30 was derived to be +/- 0.45% URL, which equates to +/- 13.50 psig. This term is inclusive of the combined effects of RAI, DR 1 , MTE 1 and PS, effects, per Ref. 4.2.1. Since this value was determined from past calibration history, it more accurately represents the transmitters performance at JAF than the vendor specified drift. Vendor specified drift will not be used.

MED30 = +/-13.5 psig 6.2.1.3. Temperature Effect (TEj)

The vendor specifies a TE of +/- (0.75% URL + 0.5% Span) per 100°F AT. The normal temperature profile is provided in Table 1 as 85°F to 100°F in the Reactor Building. Per Section 1.2.6, harsh environments will not be considered, thus TE under accident conditions will not be calculated.

0.0075x3000 + 0.005x1201x(1 00 - 885)

TENORM + 100

+/- 4.28 psig 6.2.1.4. Radiation Error (RE 1 )

The vendor specifies a RE of +/- 4% URL after a TID exposure of 2.2 x 107 rads. Per Section 1.2.6, harsh environmental effects will not be considered. In addition, any effects due to normal radiation are considered negligible. (Section 1.2.3)

Therefore, the radiation effect is negligible and, we get:

RE 1 =0 6.2.1.5. Seismic Error (SE1 )

Per Section 1.2.5, seismic effects are not applicable for these transmitters. Therefore:

SE1 =0

CALCULATION SHEET 6.2.1.6. Humidity Error (HE1 )

There are no humidity-related errors described in the vendor's specifications for this device. Per Section 1.2.4, humidity effects are considered negligible. Therefore:

HE 1 = 0 6.2.1.7. Static Pressure Error (SPj)

Static pressure effects are not applicable for gage transmitters.

SP, = 0 6.2.1.8. Power Supply Error (PS 1 )

Power supply effect is included in the MED30 term, per Ref. 4.2.1 6.2.1.9. Measuring & Test Equipment (MTEI)

MTE 1 effect is included in the MED30 term, per Ref. 4.2.1.

6.2.1.10. As-Left Tolerance (ALT,)

Per Section 5.1 and Section 1.2.2, As-Left Tolerance is +/- 0.25%

Span. Therefore; ALT,= + 0.0025 x 1200 psig = + 3.00 psig 6.2.1.11. Transmitter Module Uncertainty From Section 6.0, the general form of the device uncertainty equation is; e =+RA*+ DR2+TE2+RE- +,SE 2 +HE 2

+ SP 2 + PS 2 + MTE2 +ALT2 +B-Substituting the appropriate terms with the value of MED30, the expression for el can be rewritten as follows:

e+1 1 MD02+/-AT27+TF 2H2 E 122 2 2

+ BSp ei= +/--V/MED302 + ALT1 + TE,'oRM + RE12 + SEI + HE* + B+/-

Removing the uncertainties listed as negligible or not applicable; and setting B+/- = 0 (Since no biases were identified), we get:

e1 =+/-+MED3 + ALT2 + TELo,2"

+3.52

- + 3.02 + 4.282

- +/- 14.48 psig

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CALCULATION SHEET 22 34 Calculation Number: JAF-CALC-NBS-02052 Revision No:

4 6.2.2. ROSEMOUNT MASTER TRIP UNIT ANALOG OUTPUT (e2A).

The uncertainties determined here are applicable to the MTU analog output that feeds the STU bistable input.

6.2.2.1. Reference Accuracy - MTU Analog Output (RA 2 A)

The MTU Reference Accuracy for the MTU analog output to slave function (RA 2 A)is given in Section 5.1 as +/- 0.15% of span. The calibrated span is 1200 psig. Therefore, RA 2A =-0.15% Span

+/- 0.0015 x 1200 psig

=_1.8 psig 6.2.2.2. Drift (DR2A)

The vendor repeatability specification listed in Section 5.1 is listed as valid for up to 6 months. Since this value is taken as the device accuracy and no other specification is provided for the drift, the drift is assumed to be included in the reference accuracy (RA). Refs.

4.2.10 and 4.2.19 require a trip unit calibration every 6 months.

Therefore:

DR 2A=+ 0 psig 6.2.2.3. Temperature Error (TE 2 A)

The vendor repeatability specification listed in Section 5.1 as RA2A is valid for the normal operating range of 60°F to 90°F, per Ref.

4.3.2. Since this is binding for the Relay Room (Ref. 4.2.22), no additional temperature error is associated with the MTU.

Therefore:

TE2A =0 6.2.2.4. Humidity Error (HE2A)

There are no humidity-related errors described in the vendor's specifications for this device. Per Section 1.2.4, humidity effects are considered negligible. Therefore:

HE 2 A = 0

6.2.2.5. Radiation Error (RE 2 A)

Per Sections 1.2.3 and 1.2.10, normal radiation induced errors are assumed to be small and capable of being adjusted at each calibration. As such, normal radiation errors'are assumed to be included in the instrument accuracy term. Therefore:

RE 2A = 0 6.2.2.6. Seismic Error (SE2A)

Per Section 1.2.5, seismic effects are not applicable for these devices. Therefore:

SE 2 A 0 6.2.2.7. Static Pressure Error (SP2A)

The MTU is an electrical device and as such is not affected by static pressure changes. Therefore:

SP2A = 0 6.2.2.8. Power Supply Error (PS2A)

There are no power supply variation effects stated in the vendor's specifications for this device (Ref. 4.3.2). Therefore:

PS2A = 0 6.2.2.9. Measuring & Test Equipment (MTE 2A)

The Rosemount Digital readout assembly will be used in calibrating the Master and Slave trip units. Per Section 5.1, the readout assembly accuracy is specified as +/- 0.17% of span. Therefore, we get MTE 2A = + 17% Span

+0.0017 x 1200 psig

= + 2.04 psig 6.2.2.10. As-Left Tolerance (ALT 2A)

Per Section 5.1, As-Left Tolerance is +/- 0.1875 %Span ALT 2 A= +/- 0.001875 x 1200 psig ALT 2A= + 2.25 psig

6.2.2.11. MTU Module Uncertainty From Section 6.0, the general form of the device uncertainty equation is; e =+VRA2 + DR2 + TE2 + RE2 +SE2 + HEJ-+SP2 +PS2 + MTE2 + ALT2 + B+/-

Removing the uncertainties listed as negligible or not applicable; for the Analog function:

e2A= +/- + MTE2-A + ALT."

Substituting; e2A -1.82 +2.04 + 2.252 e2A = +/- 3.53 psig 6.2.3. ROSEMOUNT SLAVE TRIP UNIT - TRIP FUNCTION (e3T) 6.2.3.1. STU Trip Reference Accuracy (RA 3 T)

The STU Reference Accuracy for the trip function (RA 3T) is given in Section 5.1 as +/- 0.2% of span. The calibrated span is 1200 psig.

Therefore, RA 3T = +/--0.2% Span

= + 0.002 x 1200 psig

= + 2.4 psig 6.2.3.2. Drift (DR3T)

The vendor repeatability specification listed in Section 5.1 is listed as valid for up to 6 months. Since this value is taken as the device accuracy and no other specification is provided for the drift, the drift is assumed to be included in the reference accuracy (RA). Refs.

4.2.10 and 4.2.19 require a trip unit calibration every 6 months.

Therefore:

DR 3 r= +/- 0 psig 6.2.3.3. Temperature Error (TE3 T)

The vendor repeatability specification listed in Section 5.1 as RA 3 T is valid for the normal operating range of 601F to 90 0 F, per Ref.

4.3.2. Since this is binding for the Relay Room (Ref. 4.2.22), no additional temperature error is associated with the STU. Therefore:

TE 3T = 0

CALCULATION SHEET 6.2.3.4. Humidity Error (HE 3 T)

There are no humidity-related errors described in the vendor's specifications for this device. Per Section 1.2.4, humidity effects are considered negligible. Therefore:

HE3T = 0 6.2.3.5. Radiation Error (RE3T)

Per Sections 1.2.3 and 1.2.10, normal radiation induced errors are assumed to be small and capable of being adjusted at each calibration. As such, normal radiation errors are assumed to be included in the instrument accuracy term. Therefore:

RE 3 T = 0 6.2.3.6. Seismic Error (SE3T)

Per Section 1.2.5, seismic effects are not applicable for these devices. Therefore:

SE3T = 0 6.2.3.7. Static Pressure Error (SPAT)

The STU is an electrical device and as such is not affected by static pressure changes. Therefore:

SP 3 T = 0 6.2.3.8. Power Supply Error (PS3T)

There are no power supply variation effects stated in the vendor's specifications for this device (Ref. 4.3.2). Therefore:

PS3T = 0 6.2.3.9. Measuring & Test Equipment (MTE 3T)

The Rosemount Digital readout assembly error is considered in MTE 2A. Therefore:

MTE 3T = 0 6.2.3.10. As-Left Tolerance (ALT 3T)

Per Section 5.1, As-Left Tolerance is +/- 0.2 %Span ALT 3T = +/- 0.002 x 1200 psig ALT 2A= + 2.4 psig

6.2.3.11. STU Module Uncertainty From Section 6.0, the general form of the device uncertainty equation is; e =+/-VRA2 + DR2 + TE2 + RE2 +,SE2 + HE2 + SP2 + PS 2 + MTE2 + ALT2 + B+/-

Removing the uncertainties listed as negligible or not applicable; for the STU Trip function:

e3T=+ RA.+ ALT Substituting; e3T - 2.42 + 2.42 e3T = +/- 3.39 psig 6.3. TOTAL LOOP UNCERTAINTY (CU)

The general equation is found in Section 6.0. This equation is reduced to the applicable terms for each module as developed below:

CU = +J PM +PE2 p (eIR)2 + (e_)R )2 + ..... + (eR)` + B+/- + IRE Where:

PM = 0 No Primary Measurement error has been identified for this loop PE = 0 There is no Primary Element for this loop B = 0 There are no biases identified for this loop e= 14.48 psig e2A + 3.53 psig e 3 T =+3.39 psig IRE = 0 psig 6.3.1. STU Trip Function (Transmitter, MTU, & STU):

Since this is an increasing trip, only the negative uncertainties need to be considered. Using the applicable terms; CUsTU= ej + e 2,12 + I

- +/- 14.482 + 3.532 + 3.39 CUsTu +/- 15.28 Round up to include additional margin CUSTU = - 16.0 psig

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CALCULATION SHEET 27 34 Calculation Number: JAF-CALC-NBS-02052 Revision No:

4 6.4. LIMITING TRIP SETPOINT 6.4.1 Upper Limiting Trip Setpoint Per Reference 4.2.1, the Upper Limiting Trip Setpoint (LTSu) for an increasing plant parameter is given as:

LTSu = AL - CU Since this function is not credited in an accident analysis, the prescribed limit will be treated as equivalent to an analytical limit (EAL)

LTSu = EALu - CU Substituting the values for Trip uncertainty in the above equation, .we get:

LTSu = (75 - 16.0) psig (Ref 4.2.18 for the EAL)

LTSu = 59.0 psig This is the Limiting Trip Setpoint (LTS), which shall not be exceeded, in the increasing direction. The new setpoint will be set equal to the LTS (i.e.

as high as possible without challenging the Tech Spec AV) in order to reduce the likelihood of getting an isolation of SDC during noble metals application and plant outage conditions. The present field trip setpoint (FTS) of 70 psig does not reflect the uncertainties presented in this calculation and thus must be changed. The static head correction determined in references 4.2.6 and 4.2.7 has been accounted for in the transmitter calibrations and thus does not require further consideration.

Setpoint installation will be performed as part of the child ECs to EC 13686.

6.4.2 Lower Limiting Trip Setpoint Per Reference 4.2.1, the Lower Limiting Trip Setpoint (LTSL) for a decreasing plant parameter is given as:

LTSL = AL + CU÷ Since this function is not credited in an accident analysis, the prescribed limit will be treated as equivalent to an analytical limit (EAL).

LTSL = EALL + CU÷ Substituting the values for Trip uncertainty in the above equation, we get:

LTSL = 40 psig + 16.0 psig (Ref 4.2.18 for the EAL)

LTSL = 56.0 psig Therefore, the Lower Limiting Trip Setpoint (LTSL) is the lower value that the high reactor trip pressure can be set. The new Field Trip Setpoint (FTS) of 59 psig is above the calculated Lower Limiting Trip Setpoint (LTSL) of 56.0 psig, and is conservative.

CALCULATION SHEET 6.5. ALLOWABLE VALUES In accordance with Reference 4.2.1, the Allowable Value (AV) is calculated using the expressions below for the complete channel.

For increasing plant parameters the Calculated Allowable Value (CAV) is determined by:

CAV = LTS + AVTSMchannei Where:

Module AVTSMe = + VRA2 + MTE 2 + ALT 2 + DR 2 AVTSMchanneI = the statistical Combination of the module AVTSM values:

2

= +/-/AVTSMI2 + AVTSM 2 +...AVTSMJ, 6.5.1. Transmitter AVTSM The module 1 (Transmitter) AVTSM is determined by substituting MED30 for RA 1 , DR 1 and MTE 1 terms.

AVTSM, =+/-iMED30 2 + ALT,2 Substituting:

AVTSM1 =+/-/13.52 + 3.02 AVTSM1 = +13.83 psig 6.5.2. Master Trip Unit Analog Output AVTSM 2 +DR 2A AVTSMA =+__ 2 + MTE _ +ALT, Substituting for MTU:

AVTSM 2A =+/-V1.82 +2.042 + 2.252 +0.02 AVTSM 2A= +3.53 psig 6.5.3. Slave Trip Unit trip function AVTSM AVTSM3 T = RA3 T" MTE 3T" + ALT3T + DR31 -

Substituting for STU:

AVTSM 3T = 2.4 2 + 0.02 + 2.42 + 0.02 AVTSM 3T = +/-3.39 psig

6.5.4. Channel AVTSM For the trip signals T2 AVTSM(,,a =+ AVTSMJ + AVTSM 2A + AVTSM Substituting for Transmitter, MTU and STU:

= +/-_ 13.832 + 3.532 + 3.392 AVTSMChanneI = +/-14.67 psig Round up to include additional margin AVTSMchanneI = +/-15.00 psig 6.5.5. Calculated Allowable Value (CAV) 6.5.5.1. Upper Allowable Value The Upper Allowable Value is listed in the Technical Specifications.

The Calculated Upper Allowable Value (CAVu) for an increasing parameter is determined from:

CAVu = LTSu + AVTSM CAVu = (59.0 + 15.0) psig CAVu = 74.0 psig The existing Technical Specification Allowable Value (AV) of < 74 psig is acceptable since it is the same as the Calculated Allowable Value of 74.0 psig. By rounding the total AVTSM to 15.0 psig, there is a small amount of margin included in the CAV thus the Tech Spec allowable value is better protected. The AV of < 74 psig is calculated to provide protection to the EAL of 75 psig (increasing process).

6.5.5.2. Lower Allowable Values The Lower Allowable Value is listed in the Technical Requirements Manual (TRM). The Calculated Lower Allowable Value (CAVL) for a decreasing parameter is determined from:

CAVL = LTSL - AVTSM CAVL = (56.0 - 15.0) psig CAVL = 41 psig The existing Lower Allowable Value listed in the TRM (> 50 psig) represents the use of pressure switches for the SDC isolation function.

With Ref 4.2.18, the Lower EAL was reduced from 50 psig to 40 psig.

Based on the use of ATTS to provide the SDC isolation function and the change to the Lower EAL, the Lower Allowable Value must be changed to 41.0 psig. The TRM will be updated as part of EC 13686 Licensing Basis Document Change Request.

7. SCALING Scaling for the transmitter calibration is provided in JAF-CALC-NBI-001 92 and thus will not be repeated here. The Master Trip Unit analog outputs are currently checked for calibration using the ATTS Calibration Unit as part of the indication checks and STU trip checks. If the MTU analog outputs require independent calibration, refer to the vendor manual or old I&C Department procedures that calibrated the master trip unit analog output functions..

7.1. STU (Trip Function)

The input signal to STU is 4-20 mA, and the output is a trip. The new proposed field trip setpoint determined in Section 6.4 of this calculation is 59 psig (transmitter output). This value is converted to % span and milliamps, using the information from Section 5.1 as follows:

02-3STU-251A, D FTS in % span = [59 psig / 1200 psig]

• 100

= 4.916 % span FTS in mA = (4.916 % span

• 16 mA) + 4 mA

= 4.787 mA Conservatively rounding down to two decimal places, we get::

FTS in mA =4.78 mA 7.1.1. STU Trip As Found Zone (AFZ)

Per Reference 4.2.1, for Safety-Related functions the AFZ can be determined by the following equation:

AFZ 3T= +/-AVTSM 3T

=+ 3.39 psig

= + [(3.39 psig / 1200 psig)

• 16 mA] = + 0.0452 mA Conservatively rounding down to two decimal places, we get::

AFZ 3T= +/- 0.04 mA

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CALCULATION SHEET 31 34 Calculation Number: JAF-CALC-NBS-02052 Revision No:

4 7.1.2. STU Trip As Left Tolerance (ALT)

From Ref 4.2.1, the As-Left Tolerance is set equal to the RA of the device.

From Table 5.1:

ALT 3T = + 0.2 % span

= +/-2.4 psig

=+/-0.032 mA Conservatively rounding down to two decimal places, we get::

ALT 3T =+/-0.03 mA 7.2. STU Allowable Values The Allowable Values for 02-3STU-251 A, D will be scaled to support the testing units in mA:

Tech Spec Allowable Value <74 psiq 74 psig / 1200 psig

• 16 mA + 4 mA = <4.986 mA Conservatively rounding down:

<74 psig = <4.98 mA TRM Allowable Values <74 psicq and >-41 psiq 74 psig / 1200 psig

• 16 mA + 4 mA = <4.986 mA = <4.98 mA 41 psig / 1200 psig

• 16 mA + 4 mA = >4.546 mA Conservatively rounding up:

>41 psig = Ž4.55 mA

8. CONCLUSIONS The figure below shows the relation of the limits, setpoints and the allowable values.

Equivalent Analytical Limrit (EAL) _<75 psig Calculated Upper Allowable Value (CAVu) - 74 psig = AV I_________ Upper Limiting Trip Setpoint (LTSu)

Trip Setpoint

= 59 psig (INC) = Field

(

Lower Limiting Trip Setpoint (LTSL) > 56 psig (DEC)

Calculated Lower Allowable Value (CAVE) _ 41 psig =

AV Equivalent Analytical Limit (EAL) > 40 psig

8.1. RESULTS The following tables provide the calculation results.

Table 5 Function CU FTS LTS utL AV UL CAV UIL EAL Reactor Pressure +/-16 psig < 59 psig < 74 psig .. 74 psig < 75 psig SDC Permissive (4.98 mA) (4.98 mA)

(Increasing Trip) 59 psig (4.78 mA)

_ 56 psig > 41 psig > 41 psig _>40 psig (4.55 mA) (4.55 mA)

I I Table 6 Module AFZ ALT Trip Trip 02-3STU-251 A, D 0.04 mA +/- 0.03 mA

(+/-3.39 psig) (+/-2.4 psig)

CALCULATION SHEET 8.2. CONCLUSIONS 8.2.1. Revision 4 of this calculation replaces the SDC pressure switch instrument uncertainties with those that are associated with ATTS.

Due to the significant increase in instrument loop span associated with the reactor steam dome pressure measurement (1200 psig) there is a corresponding increase in instrument uncertainty. This increase in instrument uncertainty will require a change to the FTS from 70 psig to 59 psig. For the same reason, the lower allowable value in the TRM will be changed from >50 psig to Ž41 psig. The setpoints and TRM will be changed as part of EC 13686, 16226 and 16227.

8.2.2. Each instrument loop has different static head pressure that is accounted for in the transmitter calibration. Thus the transmitter output signal includes the static correction and results in the same setpoint being adjusted into each slave trip unit. The calculation results are documented in Table 5 above.

8.2.3. Use of the reactor steam dome pressure measurement (ATTS) to provide the SDC isolation function will result in the utilization of an instrument loop that has a larger instrument uncertainty than originally provided by the pressure switches. Use of a large span instrument loop to provide a relatively low pressure trip function is acceptable considering that a high accuracy measurement is not crucial for the design function. The ATTS has proven to be very accurate and highly reliable for over 20 years at JAF.

8.2.4. The AFZ and ALT as presented in Table 6 represent the use of 02-3STU-251A, D for the SDC isolation function. This acceptance criterion will be implemented as part of EC 13686, 16226 and 16227.