ML100890374

Response to Request for Additional Information for License Amendment Request for Low Temperature Overpressure Protection System Tech Specs 3.4.12, Surveillance Requirement 3.4.12.7, License Amendment Request No. 2008-04

ML100890374
Person / Time
Site:	Oconee
Issue date:	02/23/2010
From:	Baxter D Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML100890374 (30)

Text

S Duke DAVE BAXTER Vice President Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Highway Seneca, SC 29672 864-873-4460 864-873-4208 fax dabaxter@dukeenergy.

com February 23, 2010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Site, Units 1, 2, and 3 Docket Numbers 50-269, 50-270, and 50-287 Request for Additional Information for License Amendment Request for Low Temperature Overpressure Protection System Technical Specification 3.4.12, Surveillance Requirement 3.4.12.7 License Amendment Request (LAR) No. 2008-04 In accordance with 10 CFR 50.90, Duke Energy Carolinas, LLC (Duke Energy) proposes to amend Appendix A, Technical Specifications, for Renewed Facility Operating Licenses Nos.DPR-38, DPR-47, and DPR-55 for Oconee Nuclear Station (ONS), Units 1, 2, and 3. This LAR requests the Nuclear Regulatory Commission (NRC) to review and approve a change to the technical specification (TS) 3.4.12, Low Temperature Overpressure Protection (LTOP) System, surveillance requirement (SR) frequency, specifically TS SR 3.4.12.7.

TS SR 3.4.12.7 currently' requires a channel calibration to be performed every 6 months. The proposed LAR changes the TS SR frequency from 6 months to 18 months. The LAR was submitted August 6, 2009.On February 12, 2010, a request for additional information (RAI) was received from the NRC concerning documentation of the total loop uncertainty and drift for the new instrumentation.

Enclosure 1 contains the RAI responses.

Attachments 1 and 2, respectively, contain applicable sections of the calculations for the LTOP pressure instrument total loop uncertainty.

Attachment 3 contains the requested vendor information.

In accordance with Duke Energy administrative procedures and the Quality Assurance Program Topical Report, this response is still bounded by the initial review and approval of the Plant Operations Review Committee.

Additionally, a copy of this response is being sent to the State of South Carolina in accordance with 10 CFR 50.91 requirements.

Duke Energy requests that this proposed license amendment be reviewed and approved in support of the Spring, 2010 refueling outage. Duke Energy will also update applicable sections of the Oconee UFSAR, as necessary, and submit these changes per 10 CFR 50.71(e).

There are no new commitments being made as a result of this proposed change.www. duke-energy, com Nuclear Regulatory Commission License Amendment Request No. 2008-04 February 23, 2010 Page 2 Inquiries on this proposed amendment request should be directed to Reene' Gambrell of the Oconee Regulatory Compliance Group at (864) 873-3364.I declare under penalty of perjury that the foregoing is true and correct. Executed on February 23, 2010.Sincerely, Dave axter, Vice President Oco ee Nuclear Site

Enclosure:

1. Request for Additional Information, License Amendment Request for Low Temperature Overpressure Protection System Technical Specification 3.4.12, Surveillance Requirement 3.4.12.7 Attachments:

1. Calculation OSC-3862, Revision 7, Appendix F, OAC Low Range RCS Pressure Indication Uncertainty Following Implementation of NSMs OD100453, OD200454, &OD300452.2. Calculation OSC-5123, Revision 10, Appendix C, Low Range RCS Pressure Control Room Indication Uncertainty Following Implementation of NSMs OD100453, OD200454,& OD300452.3. Calculation OSC-3862, Attachment 3, Rosemount Nuclear, Model 1154 Series H Alphaline Nuclear Pressure Transmitter Nuclear Regulatory Commission License Amendment Request No. 2008-04 February 23,2010 Page 3 bc w/enclosures and attachments:

Mr. Luis Reyes, Regional Administrator U. S. Nuclear Regulatory Commission

-Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. John Stang, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8 G9A Washington, D. C. 20555 Mr. Andy Sabisch Senior Resident Inspector Oconee Nuclear Site Mrs. Susan E. Jenkins, Manager Infectious and Radioactive Waste Management Section Department of Health & Environmental Control 2600 Bull Street Columbia, SC 29201 ENCLOSURE I REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM TECHNICAL SPECIFICATION 3.4.12, SURVEILLANCE REQUIREMENT 3.4.12.7 Enclosure 1 -Request for Additional Information License Amendment Request No. 2008-04 February 23, 2010 Page 1 Request for Additional Information License Amendment Request for Low Temperature Overpressure Protection System Technical Specification 3.4.12, Surveillance Requirement 3.4.12.7 RAI #1: Provide the documentation (including sample calculations) of total loop uncertainty for the new pressure transmitter (Rosemount 1154SH9RB) to confirm that this total loop uncertainty will support existing Low Temperature Overpressure Protection (LTOP) set point evaluation analysis.RAI #1 RESPONSE: The documentation for total loop uncertainty for the new pressure transmitter is provided in Attachments 1 and 2. Attachment 1 provides the total loop uncertainty for the normal operating condition for the Operator Aid Computer (OAC) low range RCS indicator, while Attachment 2 provides the total loop uncertainty for the normal operating condition for the Control Room low range RCS pressure indicator.

RAI #2: Provide the vendor information supporting the drift of 0.2% URL over a 30 months period.RAI #2 RESPONSE: The vendor information supporting the drift of 0.2% URL over a 30 months period is included in Attachment

3.

ATTACHMENT I Calculation OSC-3862, Revision 7, Appendix F, OAC Low Range RCS Pressure Indication Uncertainty Following Implementation of NSMs OD100453, OD200454, & 0D300452.

Appendix F OAC Low Range RCS Pressure Indication Uncertainty Following Implementation of NSMs OD100453, OD200454 & OD300452 Objective This Appendix will evaluate the instrument uncertainty for the Low Range RCS Pressure channels following implementation of NSMs OD100453, OD200454 & OD300452.Background Oconee Nuclear Station is performing a Low Temperature Overpressure Protection (LTOP) System Upgrade which will upgrade the existing Train "A" of the Low Range RCS Pressure instrument loop to meet safety related, seismic and environmental qualification (EQ) requirements.

This modification will also add a new redundant Train "B" instrument loop.Modifications to Train "A" will include a replacement transmitter, power supply, current alarm module, current transmitter module and control board indicators.

A safety related Train "B" will be created using the same components.

Per Reference 44, the following components will be used as replacements in Train "A" and to create Train "B" of the Low Range RCS Pressure channel.0 Rosemount Model Number 11 54SH9RB pressure transmitters 0 Rochester XSC-1302-20012 current transmitters a Rochester XET- 1215-TI 0-20012 current alarms* Acopian VA24MT210M 24 VDC or VA36MT130M 36 VDC power supplies 0 Dixson SHI01P Single Bargraph Indicators Instrument Block Diagram Control Room eargraph~Indicator SR~ochc:stcr Roche.sler CurrPns Cureent OAC A larm Transmitter OSC-3862 Revision 7 Pane 183 MEC I.. .....

Device/Loop Uncertainty Term Identification Rosemount Model I 154SH9RB Differential Pressure Transmitters All uncertainties given in this section are for the Rosemount Model 11 54SH9RB Pressure Transmitter installed in the reactor coolant system (Reference 45). The output range for the pressure transmitters is 4 -20 mAdc corresponding to a calibrated range of 0 -600 psi.All uncertainties given below are.random-independent terms unless stated otherwise.

PT3CA -Transmitter Accuracy Per Reference 45, reference accuracy is specified as b- 0.25 % of calibrated span. Includes the combined effects of linearity, hysteresis and repeatability.

PT3CA := 0.25%span PT3D -Transmitter Drift Per Reference 45 the drift is specified as 0.2 % URIJ30 months. The URL for the the Rosemount 1154SH9RB transmitter is 3000 psig while the calibrated span is 0 -600 psig.Assuming a surveillance interval of 24 months + 25% grace period (30 months) the transmitter drift is: PT3D :- 0.2%-3000psi 600psi PT3D = 1.0% span PT3TE JTransmitter Temperature Effect Per Reference 45 the temperature effect is (0.25 % URL + 0.5 % span)/50*F between 40 'F and 130 °F. Per Table EP-1 of Reference 46, the normal reactor building temperature varies between 60 -130 OF. It is assumed that a nominal average temperature at the time of channel calibration is 80 *F. Allowing a potential temperature variation ofk 50 'F about this nominal temperature will cover the expected reactor building temeprature range. Therefore, the transmitter temperature effect is:[F(.25%-3000psi')

+ 0.5%]PT3TE = 1.75 % span OSC-3862, Revision 7 Page 184 MEC PT3TEACC -Transmitter Temperature Effect (Accident Conditions)

Per Reference 45 the accident temperature effect is (2.0 % URL -+ 0.5 % span) for a temperature profile between 420 *F at the beginning of an accident to 265 'F after 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br />.Per Table EP-I of Reference 46, the design basis accident reactor building temperature profile varies between 290 'F and 200 'F at 3.6 days (86.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). Therefore, the transmitter qualifications are bounding with respect to the qualification temperature profile given in Reference

45. This term will be conservatively treated as a two-sided bias. The transmitter temperature effect is: PT3TEA 2.20%'3000psi

+P:. 600psi ) .5 PT3TEACC=

10.5% span PT3PSE -Transmitter Power Supply Effect The Acopian 24 Vdc or 36 Vdc power supply modules will be used to supply to the transmitter.

Per Reference 47, the DC loop power supply variations are less than +/- 0.5% of the nominal supply voltage for both the VA24MT21 OM and VA36MT130M power supply models. Reference 45, gives a power supply effect of 0.005 % span/volt.

Therefore, a conservative transmitter power supply effect using the 36 Vdc model is: PSvar := 36volt-0.5%

PSvar= 0.18 volt PT3PSE:= '0.005 % -PSvarvolt)/: PT3PSE = 0.0009 % span PT3CTE -Transmitter Calibration Tolerance Effect, The transmitter calibration tolerance is assumed to be equal to the reference accuracy of 0.25% span.PT3CTE := 0-25% span OSC-3862, Revision 7 Page 185 MEC PT3SP -Transmitter Static Pressure Effect Per Reference 45 the transmitter static pressure effect is systematic and can be calibrated out for a particular pressure before installation.

The correction uncertainty is 0.5% of input reading/l,000 psi. Assuming a reading of 600 psi: PT3SP:= 600psi.5%1000psi PT3SP = 0.3% span PT3MTE -Transmitter Measurement and Test Equipment Per Reference 19 the transmitter calibration is performed using an Fluke 45 DMM or equivalent which has an uncertainty of a 0.021 mAdc on a 4 -20 mAdc range (Reference 48). Also, a Heise PTE-l with HQS-2 module Pressure Gauge with a range of 0 to 1000 psig is used. The uncertainty, as given in Reference 48 for the Heise pressure gauge, is -1.7942 psig. Both allowances above assume transmitter calibration occurs at containment temperatures between 55 'F and 92 °F.Flukerange

= 20 -4 mAdc MTE_Fluke45

= 0.021 mAdc MTE Fluke45 MTEUncFluke

.Fluke-range MTEUncFluke=0.13%

span Heise range := 1000psi -Opsi MTE Heise := 1.7942psi MTE Heise MTEUneHeise Heise range MTEUncHeise

=0.18 % span PT3MTE:= -/MTE UncFluke 2 + MTEUncHeise 2 PT3MTE = 0.22 % span OSC-3862, Revision 7 Page 186 MEC PT3RE -Transmitter Radiation Effect (Accident Conditions)

Per Table EP- I of Reference 46, the design basis accident reactor building peak radiation following a design basis accident is 61 megarads.

Per Reference 45 the accident radiation effect is (0.5 % URL + 1.0 % span) up to 55 megarads and (0.75 % URL + 1.0 % span) after a 110 megarads.

Since the peak radiation effect is above 55 megarads and is not expected to be above I 10 megarads the accuracy for 110 megarads will conservatively be used. This term will be conservatively treated as a two-sided bias. The transmitter radiation effect is: PT3RE: .f( 0.75%-30O0psi>

+ l.O~L(0 7 3600psi ) %J PT3RE = 4.75 % span PT3PMA -Process Measurement Allowance (Normal Conditions)

Per Reference 51 the normal reactor building pressure can vary between -2.45 psig and +1.2 psig. Therefore, a conservative allowance of-+/- 3 psig is used bound this reactor building pressure variation.

This term will be conservatively treated as a two-sided bias. The normal conditions process measurement allowance is: 3.0psi PT3PMA .-600psi PT3PMA 0.5 % span Combination of Normal Conditions Transmitter Error Terms TLULRPress Xmtr := PT3CA 2 + PT3D 2 -+ PT3TE 2 + + PT3CTE 2 ... + PT3PMA J+ PT3SP2 + PT3MTE 2 TLULRPress Xmtr = 2.58% span CADHD -Current Alarm Hardware Effects Per Reference 49, reference accuracy is specified as +/- 0.1 % of span.CADHD:= 0.1% span OSC-3862, Revision 7 Page 187 MEC 9CADPSE -Current Alarm Power Supply Effect The Acopian 24 Vdc or 36 Vdc power supply modules will be used to supply to the current alarm. Per Reference 47, the DC loop power supply variations are less than +/- 0.5% of the nominal supply voltage for both the VA24MT2 IOM and VA36MT 130M power supply models.Reference 49, gives a power supply effecit of 0.15 % for a variation in voltage of 20%.Therefore, a current alarm power supply effect is: CADPSE := 0.15% span CADCTE -Current Alarm Calibration Tolerance Effect The transmitter calibration tolerance is assumed to be equal to the reference accuracy of 0.1 %span.CADCTE:= 0.1% span CADMTE -Current Alarm Measurement and Test Equipment Per Reference 19 the transmitter calibration is performed using a Heise PTE-t with HQS-2 module Pressure Gauge with a range of 0 to 1000 psig. The uncertainty, as given in Reference 48 for the Heise pressure gauge, is h 1.7942 psig.CADMTE := MTEUncHeise CADMTE =0.18 % span CTHD -Current Transmitter Hardware Effects Per Reference 50, linearity and repeatability are each specified as -0.1% of span therefore,ýthe reference accuracy is: CTHD:= 0.1%)2 + (0.1%)2 CTHD =0.141% span CTPSE -Current Transmitter Power Supply Effect The Acopian 24 Vdc or 36 Vdc power supply modules will be used to supply to the curre'nt transmitter.

Per Reference 47, the DC loop power supply variations are less than

• 0.5% of the nominal supply voltage for both the VA24MT2iOM and VA36MTI30M power supply models. Reference 50, gives a power supply effect of 0.15 % for a variation in voltage of 20%. Therefore, a current alarm power supply effect is: CTPSE:= 0.15% span OSC-3862, Revision 7 Page 188 MEC CTCTE -Current Transmitter Calibration Tolerance Effect The transmitter calibration tolerance is assumed to be equal to the reference accuracy of 0.141% span.CTCTE:= CTHD CTCTE = 0.141% span CTMTE -Current Transmitter Measurement and Test Equipment Per Reference 19 the transmitter calibration is performed using a Heise PTE- I with HQS-2 module Pressure Gauge with a range of 0 to 1000 psig. The uncertainty, as given in Reference 48 for the Heise pressure gauge, is :L 1.7942 psig.CTMTE;= MTEUncHeise CTMTE = 0.18 % span CTTE -Current Transmitter Temperature Effect Per Reference 50 the temperature effect is 0.02 %P'F between 25 *F and 125 'F. Per Reference 48 the normal expected environmental conditions in the control complex are 74 -80'F. Therefore the temperature effect is: CTTE:= [0.02%-(80

-74)]CTTE = 0.12% span OAC -Indicator Accuracy Per Table 7.4 of Reference 52 for a 4 -20 mA input the bounding OAC uncertainty is 0.156%span. This uncertainty includes the computer accuracy, temperature, drift and other miscellaneous effects.OAC:= 0. 156% span 0 OSC-3862, Revision 7 Page 189.MEC OAC Low Range RCS Pressure Total Loop Uncertainy (Normal Conditions)

TLUOACLRPress:=

TLULRPressXmtr

+ CADHD + CADPSE + CADCTE + CADMTE .../+ CTHD2+ CTPSE2+ CTCTE2 CTMTE2 CTT-E+ OAC2 TLU_OACLRPress

= 2.62 % span OACLowRangePress

= TLU_OACLRPress-600psi OACLowRange._Press

= 15.72 psi OAC Low Range RCS Pressure Total Loop Uncertainy (Accident Conditions) 2 2 2 TLUOACLRPAcc

= TLULRPressXmtr

+ CADHD + CADPSE ... + PT3TEACC + PT3RE+CADCTE2 + CADMTE2 + CTHD2 + CTPSE2 ...+ CTCTE2 + CTMTE 2 + CITE 2 + OAC2 TLUOACLRPAcc

17.87% span OACLRPress_Acc:

TLUOACLRPAcc.600psi OACLRkPress Acc = 107.22psi Results The Low Range Pressure uncertianties used to produce the OAC subcooling indication are summarized below.OAC Low Range RCS Pressure Total Loop Uncertainy Normal Conditions:

OACLowRangePress

= 15.7 psi Accident Conditions:

OACLRPressAce

= 107.2 psi OSC-3862, Revision 7 Page 190 MEC Conclusions The normal condition Low Range Pressure uncertainty results calculated above are within the results calculated previously for this channel (15.7 psi vs. 18.8 psi). An uncertainty allowance of+/- 25.0 psi was used previously to develop the OAC subcooled margin monitor curves in Tables 16, 18 and 20.Therefore, the curves in Tables 16, 18 and 20 and their associated polynomials will not need to be revised.The accident condition Low Range Pressure uncertainties presented above are for possible future use as it may be desirable to use the new instrumentation under degraded reactor building conditions for post accident monitoring.

OSC-3862, Revision 7 Page 191 MEC ATTACH-MENT 2 Calculation OSC-5123, Revision 10, Appendix C, Low Range RCS Pressure Control Room Indication Uncertainty Following Implementation of NSMs OD1300453, OD200454, &0D300452.\

Appendix C Low Range RCS Pressure Control Room Indication Uncertainty Following Implementation of NSMs OD100453, OD200454 & OD300452 Objective This Appendix will evaluate the instrument uncertainty for the Low Range RCS Pressure control room indication following implementation of NSMs 0D100453, OD200454 & 0D300452.Background Oconee Nuclear Station is performing a Low Temperature Overpressure Protection (LTOP) System Upgrade which will upgrade the existing Train "A" of the Low Range RCS Pressure insiniment loop to meet safety related, seismic and environmental qualification (EQ) requirements.

This modification will also add a new redundant Train "B" instrument loop.Modifications to Train "A" will include a replacement transmitter, power supply, current alarm module, current transmitter module and control board indicators.

A safety related'Train "B" will be created using the same components.

Per Reference 8.34, the following components will be used as replacements in Train "A" and to create Train "B" of the Low Range RCS Pressure channel.0 Rosemount Model Number 11 54SH9RB pressure transmitters

• Rochester XSC-1302-20012 current transmitters

• Rochester XET-1215-TIO-20012 current alarms& Acopian VA24MT210M 24 VDC or VA36MT130M 36 VDC power supplies* Dixson SHI01P Single Bargraph Indicators Instrument Block Diagram Control Room@ *Bargraph Indicator Rochester Rochester Current Current OAC Alarm Transrmitter 0 OSC-5123, Revision 10 Page 39 MEC Device/Loop Uncertainty Term Identification Rosemount Model I I 54SH9RB Differential Pressure Transmitters All uncertainties given in this section are for the Rosemount Model 1-1 54SHg9RB Pressure Transmitter installed in the reactor coolant system (Reference 8.35). The output range for the pressure transmitters is 4 -20 mAdc corresponding to a'calibrated range of 0 -600 psi.: All uncertainties given below are random-independent terms unless stated otherwise.

P4PTCA -Transmitter Accuracy Per Reference 8.35, reference accuracy is specified as + 0.25 % of calibrated span. Includes the combined effects of linearity, hysteresis and r'epeatability.

P4PTCA 0.25% span P4PTD -Transmitter Drift Per Reference 8.35 the drift is specified as 0.2 % URL/30 months. The URL for the the Rosemount 1 154SH9RB transmitter is 3000 psig while the calibrated span is 0 -600 psig.Assuming a surveillance interval of 24 months + 25% grace period (30 months) the transmitter drift is: 0.2%- 3000psi P4PTD .600psi P4PTD = 1.0% span P4PTTE- Transmitter Temperature Effect Per Reference.

8.35 the temperature effect is (0.25 % URL + 0.5 % span)/50 0 F between 40 IF and 130 'F. Per Table EP-I of Reference 8.36, the normal reactor building temperature varies between 60 -130 IF. It is assumed that a nominal average temperature at the time of channel calibration is 80 IF. Allowing a potential temperature variation of+/- 50 IF about this nominal temperature will cover the expected reactor building temeprature range. Therefore, the transmitter temperature effect is: PT 0.25%-3000psi)

+/-P4PTTE..-Lý-

+ 05 L( 600psi P4PTTIE 1.75% span 0 OSC-5123, Revision 10 Page 40 MEC P4PTTEACC

-Transmitter Temperature Effect (Accident Conditions)

Per Reference 8.35 the accident temperature effect is (2.0 % URL + 0.5 % span) for a temperature profile between 420 IF at the beginning of an accident to 265 OF after 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br />.Per Table EP-I of Reference 8.36, the design basis accident reactor building temperature profile varies between 290 OF and 200 OF at 3.6 days (86.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). Therefore, the transmitter qualifications are bounding with respect to the qualification temperature profile given in Reference 8.35. This term will be conservatively treated as a two-sided bias. The transmitter temperature effect is:%.3000psi

.%]P4PTTEACC I=Lk 600psi' )P4PTT'EACC

= 10.5 % span P4PTPSE -Transmitter Power Supply Effect The Acopian 24 Vdc or 36 Vdc power supply modules will be used to supply to the transmitter.

Per Reference 8-37, the DC loop power supply variations are less than + 0.5%of the nominal supply voltage for both the VA24MT21 OM and VA36MT130M power supply models. Reference 8.35, gives a power supply effect of 0.005 % span/volt.

Therefore, a conservative transmitter power supply effect using the 36 Vdc model is: PSvar := 36volt. 0.5% PSvar = 0.18 volt P4PTPSE (0.005 vo -PSvar P4PTPSE =0.0009% span P4PTCTE -Transmitter Calibration Tolerance Effect The transmitter calibration tolerance is assumed to be equal to the reference accuracy of 0.25 % span.P4PTCTE := 0.25% span OSC-5123, Revision 10 Page 41 MEC P4PTSP -Transmitter Static Pressure Effect Per Reference 8.35 the transmitter static pressure effect is systematic and can be calibrated out for a particular pressure before installation.

The correction uncertainty is 0.5% of input reading/I,000 psi. Assuming a reading of 600 psi: P4PTSP 600psi 0.5%1000psi P4PTSP = 0.3 % span P4PTMTE -Transmitter Measurement and Test Equipment Per Reference 8.38 the transmitter calibration is performed using an Fluke 45 DMM or equivalent which has an uncertainty of :L 0.021 mAdc on a 4 -20 mAde range (Reference 8.39). Also, a Heise PTE-1 with HQS-2 module Pressure Gauge with a range of 0 to 1000 psig is used. The uncertainty, as given in Reference 8.39 for the Heise pressure gauge, is +1.7942 psig. Both allowances above assume transmitter calibration occurs at containment temperatures between 55 IF and 92 'F.Fluke_range

= 20 -4 mAdc 0 MTEFluke45

= 0.021 mAdc MTE Fluke45 MTEUncFluke

Fluke-range MTEhUnc.Fluke

= 0.13 t/ span Heisejrange

- 1000psi -Opsi MTEHeise := 1.7942psi MTE Heise MTEUncHeise

=Heise range MTE_Unc_Heise

= 0.18 *' span P4PTMTE := ]MTEUnc_.Fluke 2 + MTEUnc Heise 2 P4PTMTE = 0.22 % span OSC-5123, Revision 10 Page 42 MEC P4PTRE -Transmitter Radiation Effect (Accident Conditions)

Per Table EP-I of Reference 8.36 design basis accident reactor building peak radiation following a design basis accident is 61 megarads.

Per Reference 8.35 accident radiation effect is (0.5 % URL + 1.0 % span) up to 55 megarads and (0.75 % URL + 1.0 % span) after a 110 megarads.

Since the peak radiation effect is above 55 megarads and is not expected to be above 110 megarads the accuracy for I 10 megarads will conservatively be used. This term will be conservatively treated as a two-sided bias. The transmitter radiation effect is: P4PTRE " 0.75%' 3000psi+ 1" PTE -600psi .+'P4PTRE = 4.75 % span P4PTPMA -Process Measurement Allowance (Normal Conditions)

Per Reference 8.11 the normal reactor building pressure can vary between -2.45 psig and + 1-2 psig. Therefore, a conservative allowance of zk 3 psig is used bound this reactor building pressure variation.

This term will be conservatively treated as a two-sided bias. The normal conditions process measurement allowance is: P4PTPMA. 3.Opsi 600psi P4PTPMA =0.5% span Combination of Normal Conditions Transmitter Error Terms 2 2 2 2 TLULRPressXntr:=

P4PTCA + P4PTD + P4PTTE2 + P4PTPSE .. + P4PTPMA 1+ P4PTCTE2 + P4PTSP2 + P4PTMTE2 TLULRPress_Xrmtr

= 2.58 % span P4ICA -Indicator Reference Accuracy Per Reference 8.40, the indicator reference accuracy is specified as + 0.04 % of calibrated span +/- I count. I count is defined as the + unit value of the rightmost digit. Since the display is a four digit display I count will equal 0. 1 psig.P41CA 0.04%.600psi

+ 0.1psi 600psi P4ICA = 0.057 % span OSC-5 123, Revision 10 Page 43 MEC P41D -Indicator Drift Per Reference 8.40, the indicator drift is +/- 0.0 15% of calibrated span per month. Assuming a surveillance interval of 24 months + 25% grace period (30 months) the indicator drift is: mon := 30day P41D := 0.015-.30mon mon P41D = 0.5% span P4IRA -Indicator Readability Per Reference 8.40, the display is a four digit display capable of displaying any value between -9999 and +9999. Therefore, the rightmost digit on a 0 -600 psig range will be able to resolve pressure at 0. 1 psig increments.

0.lpsi P41RA .600psi P4IRA = 0.017% span P41OTE -Indicator Ambient Temperature Change Offset Error Per Reference 8.40 the ambient temperature change offset error is 0.01 % calibrated span/C.Per Reference 8.36 Table EP-3, the normal expected environmental conditions in the control complex are 74 -80 *F (23.3 -26.7 1C). Therefore the temperature change offset error is: P4IOTE := 0.01%-(26.7

-23.3)P4IOTE = 0.034% span P4IGTE -Indicator Ambient Temperature Change Gain Error Per Reference 8.40 the ambient temperature change gain error is 0.02 % full scalet'C.

Per Reference 8.36 Table EP-3, the normal expected environmental conditions in the control complex are 74 -80 'F (23.3 -26.7 °C). Therefore the temperature change offset error is: P41GTE := 0.02%.(26.7

-23.3)P4IGTE = 0.068% span OSC-5123, Revision 10 Page 44 MEC P41CTE -Indicator Calibration Tolerance Effect Per Reference 8.38 the indicator calibration tolerance is 0.1 % span.P4ICTE := 0.1% span P4IMTE -Indicator Measurement and Test Equipment Per Reference 8.38 the indicator calibration is performed using a Heise PTE-l with HQS-2 module Pressure Gauge with a range of 0 to 1000 psig. The uncertainty, as given in Reference 8.39 for the Heise pressure gauge, is +/-: 1.7942 psig.P4IMTE:= MTEUncHeise P4IMTE = 0.18 % span Control Room Indication Low Range RCS Pressure Total Loop Uncertainy (Normal Conditions)

ThUCR=_LRPress ITLULRPressXmtr2

+ P41CA2 + P4ID2 + P4IRA2 + P4IOTE2-+- P4IGTE2 + P4ICTE2 + P41MTE2 TLU_CRILRPress

2.63 % span IND_LowRangePress:

TLU_CR1_LRPress-600psi INDLowRange._Press

= 15.77 psi Control Room Indication Low Range RCS Pressure Total Loop Uncertainy (Accident Conditions)

TLU CR1 LRPAcc := TLU LRPressXmtr2

+ P41CA2 + P4ID .2. + P4PTTEACC

+ P4PTRE+ P4[RA2 + P41OTE2 + P4IGTE2 2 2+ P4ICTE2 + P4IMTE2 TLUCRILR.PAcc

= 17.88% span INDLRPress_Ac

= TLUCRILRPAcc.600psi INDLRPressAcc--

107.27psi OSC-5123, Revision 10 Page 45 MEC Results The Low Range Pressure uncertianties used to produce the control room indication are summarized below.Control Room Indication Low Range RCS Pressure Total Loop Uncertainy Normal Conditions:

Two-sided:

INDLow RangePress

= 15.8 psi One-sided:

OSIND_LowRangePress

= IND_Low_Range Press. 0.84 OS_IND_LowRange._Press 13.2 psi Accident Conditions:

Two-sided:

INDLRPressAce

= 107.3 psi One-sided:

OSINDLRPressAcc IND)LRPressAcc-0.84 OSINDLRPressAcc

= 90.1 psi Conclusions The normal condition Low Range Pressure uncertainty results calculated above are within the results calculated previously for this channel indication (13.2 psi vs. 20.6 psi). The results for the new instrumentation is also within the low pressure indication uncertainty sensitivity case results presented in Tables C-2 and C-3 (13.2 psi vs. 13.86 and 15.43 psi). Therefore, the sensitivity cases will not be reanaylzed for the new instrumentation in this appendix.The accident condition Low Range Pressure indication uncertainties presented above are for possible future use as it may be desirable to use the new instrumentation under degraded reactor building conditions.

OSC-5123, Revision 10 Page 46 MEC ATTACHMENT 3 OSC-3862, Attachment 3 Rosemount Nuclear Model 1154 Series H Alphaline Nuclear Pressure Transmitter 0 0813-0100-4631 English June 1999 Rev. AA Model 1154 Series H Alphaline Nuclear Pressure Transmitter K ROSEMOUNT" NUCLE.AR=4.,-._. §w*wnM l ()-C -394,2 Model 1154 Series H Alphaline Nuclear Pressure Transmitter FEATURES O Qualified per IEEE Std 323-1974 and IEEE Std 344-1975* 1.1 x 108 rads TID gamma radiation 0 8.5 g ZPA seismic* 420 OF (215.6 'C) steam temperature

• 0.25% accuracy INTRODUCTION Model 1154 Series H Alphaline Nuclear Pressure Transmitters are designed for precision pressure measurements in nuclear applications that require reliable performance and safety over a specified qualilied life. These transmitters were qualified per IEEE Std 323-1974 and IEEE Std 344-1975 at radiation levels of 110 megarads TID gamma radiation, seismic levels of 8.5 g, and fbr steam-pressure performance.

Stringent quality control during the manufacturing process includes traceability of pressure-retaining parts, special nuclear cleaning, and hydrostatic testing.TRANSMITTER DESCRIPTION Model 1154 Series H Transmitters are uniquely built for Class 1E nuclear service, while retaining the basic design of the Model 1151 Series that has become a standard of reliable service. Units are available in sealed reference (S), differential (D), and high-line differential (H) configurations, with a total of six pressure range options.Direct electronic sensing with the completely sealed 6-Cell" capacitance sensing element eliminates mechanical force transfer and problems associated with shock and vibration.

Installation and commissioning are simplified by the compact design and 2-wire system compatibility.

Wuring terminals and electronics are in separate compartments, so the electronics remain sealed during installation.

The Model 7 154 Seres H Atphaffne Nucear Pasure TwnsrmIter may be protwCod by one or more of the fOiwI Us. Pat No& and Re.30,60a may depend on Model. Otter Forelgn PatntWs ls&ued end Penawng Flsher-Rosemount salls-fis all oblgations coming from.E legislation to harmonlze product requirements in the European Union.2 gm 0)n FIGURE 1. The &-Cell Sensor.OPERATION The completely sealed &Cell capacitance sensing element is the key to the unequalled performance and reliability of the Model 1154 Series H Pres.sure Transmitter.

Process pressure is transmitted through an isolating diaphragm and silicone oil fill fluid to a sensing diaphragm in the center of the 8-Cell (see Figure 1). A reference pressure is transmitted in the same manner to the other side of the sensing diaphragm.

Displacement of the sensing diaphragm, a maximum motion of 0.004 in. (0.1 mm), is proportional to the pressure differential across it- The position of the sensing diaphragm is detected by capacitor plates on both sides.Differential capacitance between the sensing diaphragm and the capacitor plates is converted electronically to a 2-wire, 4-20 mAde signal.Rosemount, Me Rosemount ogo, and Aiphne are registered tradefnafk and iCs e isademaak of Rosmnount lr, Swagdlok is a regisered btadefmrk of Crmword Fd1ing Co.Cover P~loto 1154-OOIAC 0 yC- 39 7_PQt'j r- 2 , 1 14QC ,.kA&,+ f Model 1154 Series H AlphalineO Nuclear Pressure Transmitter SPECIFICATIONS

• Nuclear Specifications Qualified per IEEE Std. 323-1974 and 344-1975, as stated in Rosemount Report D8700096 Radiation Accuracy within +/-(0.25% of upper range limit 4.0.75% of span) during first 30 minutes; *(0.5% of upper range limit + 1.0% of span) thereafter up to 55 megarads total integrated dosage (TID); +/-(0.75% of upper range limit + 1.0% of span) after 110 megarads TID gamma radiation exposure Seismic Accuracy within +/-0.5% of upper range limit during and after a disturbance defined by a required response spectrum with a horizontal ZPA of 8.5 g, and a vertical ZPA of 5.2 g Steam Pressure/Temperature Accuracy within +/-(1.0% of upper range limit + 1.0%of span) for range codes 4-8; +/-(2.0% of upper range limit + 0.5% of span) for range code 9 during and )after sequential exposure to steam at the following temperatures and pressures,, concurrent with chemical spray for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 420 OF (215.6 °C), 85 psig for 3 minutes 350 'F (176.6 'C), 85 psig for 7 minutes 320 °F (160 C), 75 psig for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 265°'F (129.4 -C), 24 psig for 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> Chemical Spray Chemical spray composition is 0.28 molar boric acid, 0.064 sodium thiosulfate, and sodium hydroxide, to make an initial pH of 11.0 and a subsequent pH ranging from 8.5 to 11.0. Chemical spray is sprayed at a rate of 0.25 galmin/ft 2.Post DUE Operation Accuracy at reference conditions shall be within+/-2.5% of upper range limit for one year following DBE.Quality Assurance Program In accordance with NQA-1, 10CFRSO Appendix B, and ISO 9001 Nuclear Cleaning To 1 ppm maximum chloride content Hydrostatic Testing To 150% of maximum working pressure or 2,000 psi (13.8 MPa), whichever is greater Traceability In accordance with NQA-1 and IOCFR50 Appendix B;chemical and physical material certification of pressure-retaining parts 4-OSC-3k 2_Qualified Life Dependent on continuous ambient temperature at the installation site, illustrated in Figure 3.Replacement of amplifier and calibration circuit boards at the end of their qualified life permits extension of the transmitter's qualified life to the module's qualified life. See Rosemount Report D8700096.0 0 E I.Module Electronics Qualifed Life W0 W0 10D 110 12 1W0 14 110 Temperature

('F)FIGURE 3. Qualified Life vs. Ambient Temperature.

Performance Specifications Based on zero-based ranges under reference conditions Accuracy+/- -02,5% of calibrated span; includes combined effects of linearity, hysteresis, and repeatability Dead Band None Drift+/-0.2% of upper range limit for thirty months Temperature Effect Ranges 4-8:+/-(0.15% upper range limit + 0.35% span) per 50 °F (27.8 °C) ambient temperature change between 40 'F (4.4 'C) and 130 OF (54.4 °C)Range 9:+/-(0.25% of upper range limit + 0.5% span) per , 50 °F (27.8 '0) ambient temperature change between 40 'F (4.4 'C) and 130 OF (54.4 '0)All Ranges:+/-(0.75% of upper range limit + 0.5% span) per 100 OF (55.6 'C) ambient temperature change between 40 'F (4.4 'C) and 200 'F (9383 °C)P&3-e 3 0 f-4 A ft 4 d , 0.4 1 -Rosemount Nuclear Instruments, Inc.Overpressure Effect Model 1154DH:.Maximum zero shift after 2,000 psi (13.8 MPa)overpressure:

4 +/-0.25% of upper range lrnt 5 1.0% o upper range liner 6-7 +/-3.0% of upper range Irmit 8 *6-0% of upper range Urnit Model 1154HH: Maximum zero shift after 3,000 psi (20.68 MPa)overpressure:.

Response Time Fixed time constant (63%) at 100 °F (37.8 C): 4 , 0.5 seconds or less all others 0.2 seconds or less I Adjustable damping option is available through special N-Option.Functional Specifications Service Liquid, gas, or vapor Output 4-20 mA dc Power Supply Design limits are as shown in Figure 4. See Rosemount Report D8700096 for additional detail.Range ~ .. CoeOepesueEfc 4 *1.0% of upper range limit 5 t2.0% of upper range lirnit_-7-_. L5.0% of upper range lrmi,/Model 1154SH3)MAaximuim-zero shift after 4,500 psi (31.0 MPa)overpressure:

____*) +/-O,% otupper On lirnit Static Pressure Zero Effect Model 1154DH: Per 1,000 psi (6.89 MPa): 4-5 +/-10.2% of upper rnge 01Imi Model 1154HH: Per 1,000 psi (6.89 MPa): 4-A+/-.W8% of upper rang limit _Static Pressure Span Effect Effect is systematic and can be calibrated out for a particular pressure before installation; correction uncertainty:.

+/-0.5% of input reading/1,000 psi (6.89 MPa)Power Supply Effect -.Less than 0.005% of output span/volt Load Effect No load effect other than the change in voltage supplied to the transmitter Mounting Position Effect No span effect; zero shift of up to 1.5 inH 2 0 (372 Pa), which can be calibrated out 18-5 1 1000-.- Soo-3 o 4-20 mA d2-Quallffed Region Design Region I T E Power Supply (V dc)FIGURE 4. Load ULiitallons.

Span and Zero Continuously adjustable, externally Zero Elevation and Suppression Maximum Zero Elevation:

600% of calibrated span Maximum Zero Suppression:

500% of calibrated span Zero elevation and suppression must be such that neither the calibrated span nor upper or lower range value exceeds 100% of upper range limit.Temperature ULmits Normal Operating Limits: 40 to 200 °F (4.4 to 93.3 'C)Qualified Storage Limits: -40 to 120 °F (-40.0 to 48.9 °C)Humidity Limits 0-100% relative humidity (NEMA 4X)Volumetric Displacement Less than 0.01 cubic in. (0.16 cm 3)Turn-On Time 2 seconds maximum. No warm-up required 5 Page. q 0-rtl Model 1154 Series H Alphaline 5 Nuclear Pressure Transmitter Pressure Ranges Models 1154DH and 1154HH: 4 0-25 to 0-150 InH20 (0-6.22 to 0-37.3 kia)5 0-125 to 0-750 inH 2 0 (0-3 1.08 to 0-156.4 kPa)6 0-17 to 0-100 psi (0-0.12 Io 0-0.69 MPa)7 0-SO to 0-300 psf (0-0.34 to 0-2.07 MPa)8 0-170 to 0-1,000 psi (Model 1154 D only)(0.-1 .17 to 0-6.89 MPa)(9,, 0-SOOto 0--3.000 psi (0-3.45 to 0-20.6 MPA)Maximum Working Pressure Model 11$4DH and 1154HH: Static Pressure Limit Model 1154SH: Upper range limit Static Pressure and Overpressure Limits Model 1154DH: 0.5 psia to 2,000 psig (3.4 kPa abs to 13.8 MPa)maximum rated static pressure for operation within specifications; overpressure limit is 2,000 psig (13.8 vPa) on either side without damage to the transmitter

• Model 11154HH: 0.5 psia to 3,000 psig (3.4 kPa abs to 20.7 MPa)maximum rated static pressure for operation within specifications; overpressure limit is 3,000 psig (20.7 MIa) on either side without damage to the transmitter Overpressure Limits Model 1154SH: Operates within specification from 0.5 psia (3.4 kPa abs) to upper range limit; overpressure limit is 4,500 psig (31.0 MPa) for range code 9, without damage to the transmitter Physical Specifications Materials of Construction Isolating Diaphragms:

316L SST DrainNent Valves: 316 SST Process Flanges: CF-8M (cast version of 316 SST)6 Proces-s O-rings: 316L SST Electronics Housing O-rings: Ethylene Propylene Fill Fluid: Silicone Oil Flange Bolts: Plated Alloy Steel, per ASTM A-540 Electronics Housing: 316 SST Module Shroud: 304L SST Module Shroud Potting: Silicone RTV Mounting Bracket: 316L SST Mounting Bolts: SAE J429 Carbon Steel, Grade 2 or Grade 5 Weight 26.6 lb (12.1 kg) including mounting bracket Electrical Connections 11-14 NPT conduit with screw terminals Process Connections

/a-inch Swagelok compression fitting, 316 SST (V4-18 NPT optional)6)5C -,3. 2-