ML102040138

License Amendment Request 261 Extended Power Uprate, Transmittal of Sample Reactor Protection System/Engineered Safety Features Actuation System Instrumentation Setpoint Calculations

ML102040138
Person / Time
Site:	Point Beach
Issue date:	07/21/2010
From:	Meyer L Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2010-0113
Download: ML102040138 (182)

Text

July 21,2010 NRC 2010-0113 i 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Reauest 261 Extended Power Uprate Transmittal of Sample Reactor Protection Svstem / Enaineered Safetv Features Actuation Svstem Instrumentation Set~ointCalculations

References:

(1) FPL Energy Point Beach, LLC letter to NRC, dated April 7,2009, License Amendment Request 261, Extended Power Uprate (ML091250564)

(2) NextEra Energy Point Beach, LLC, Letter to NRC, dated December 8,2009, License Amendment Request 261 Supplement 3, Extended Power Uprate (ML093430114)

I (3) NRC electronic mail to NextEra Energy point Beach, LLC, dated November 2,2009, Point Beach Nuclear Plant, Units 1 and 2 - Request for Additional lnformation from lnstrument and Control Branch RE: Non-conservative Technical Specifications (ML093060170)

(4) NextEra Energy Point Beach, LLC letter to NRC, dated November 30,2009, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional lnformation (ML093360143)

~~

(5) NRC electronic mail to NextEra Energy point Beach, LLC, dated March 25, 2010, DRAFT - Request for Additional lnformation from lnstrument and Control Branch RE: EPU (ML100840783)

(6) NextEra Energy Point Beach, LLC letter to NRC, dated April 30, 2010, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional lnformation (MLI01200544)

NextEra Energy Point Beach, LLC (NextEra) submitted License Amendment Request (LAR) 261 (Reference 1) to the NRC pursuant to 10 CFR 50.90. The proposed amendment would increase each unit's licensed thermal power level from 1540 megawatts thermal (MWt) to 1800 MWt, and revise the Technical Specifications (TS) to support operation at the increased thermal power level.

NextEra Energy Point Beach, LLC,6610 Nuclear Road, Two Rivers, WI 54241

Document Control Desk Page 2 Supplement 3 to LAR 261 (Reference 2) was submitted to the NRC to provide revised proposed changes for the reactor protection system (RPS) lnstrumentation TS Table 3.3.1-1 and engineered safety features actuation system (ESFAS) lnstrumentationTS Table 3.3.2-1. The proposed changes provided in Reference (2) included both extended power uprate (EPU) related and non-EPU related changes. The proposed changes also included the addition of a new column, Nominal Trip Setpoint. This column was added in order to be consistent with the TS Table format in NUREG 1431, Standard Technical Specifications - Westinghouse Plants, and Technical Specification Task Force (TSTF)-493, Revision 4, Clarify the Application of Setpoint Methodology for Limiting Safety System Setting (LSSS) functions.

Via electronic mail dated November 2, 2009 (Reference 3), the NRC requested additional information to support its review of the RPSIESFAS TS changes. Reference (4) provided NextEra's response to the NRC request and included four sample uncertainty calculations for RPSIESFAS setpoints to support the response to RAI EICB-RAI-2. Via electronic mail dated March 25, 2010 (Reference 5), additional calculations were requested to support the response to RAI EICB-RAI-2. Reference (6) provided two additional sample calculations for RPSIESFAS setpoints affected by EPU.

Per telecon on May 6, 2010, the NRC staff notified NextEra that determining LSSSs using single-sided random uncertainties was not acceptable and that the RPSIESFAS calculations that used single sided uncertainty factors would have to be revised. As a result, NextEra revised the RPSIESFAS instrumentation uncertaintylsetpoint calculations to eliminate the use of a single-sided reduction factor in the total loop error determination for LSSSs. The revised calculations require changes to some TS allowable values and nominal trip setpoints previously provided in References (4) and (6). These changes are being submitted to the NRC under separate correspondence.

It was requested that the revisions to the sample calculations eliminating the single-sided reduction factor be submitted. Five of the six sample calculations previously submitted were revised to eliminate the single-sided reduction factor. Calc 2007-0001, Turbine Impulse Pressure Low Power Permissive P-7 lnstrument Scaling and Uncertainty, did not include single-sided uncertainties, and as a result does not require revision or resubmittal. The remaining five calculations have minor revisions that eliminate the single-sided reduction factor and supplement the full calculations that were previously sent to NRC. The uncertaintylsetpoint calculations with minor revisions are listed below and are Attachments 1 through 5 to Enclosure 1 as follows:

These minor revisions convert the uncertainties to double-sided.

Attachment 1 2009-0001-000-A Pressurizer Pressure Instrument Loop UncertaintyISetpointCalculation Attachment 2 2009-0002-000-A Power Range Nuclear Instrumentation UncertaintyISetpointCalculation Attachment 3 PBNP-IC-17-003-A Low Range Containment Pressure UncertaintylSetpoint Calculation

Document Control Desk Page 3 Attachment 4 PBNP-IC-39-004-A Steam Line Pressure Instrument Loop UncertaintyISetpoint Calculation Attachment 5 97-0231-002-C Auxiliary Feedwater Pumps Low Suction Pressure SW Switchover UncertaintyISetpointCalculation This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.

In accordance with 10 CFR 50.91, a copy of this letter is being provided to the designated Wisconsin Official.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on July 21,2010.

Very truly yours, NextEra Energy Point Beach, LLC Larry Meyer Site Vice President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW

ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 261, EXTENDED POWER UPRATE TRANSMI'ITAL OF SAMPLE CALCULATIONS FOR REACTOR PROTECTION SYSTEM / ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SETPOINT CALCUATIONS 178 pages follow

ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 261, EXTENDED POWER UPRATE TRANSMIlTAL OF SAMPLE CALCULATIONS FOR REACTOR PROTECTION SYSTEM IENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SETPOINT CALCUATIONS AlTACHMENT 1 PRESSURIZER PRESSURE INSTRUMENT LOOP

- UNCERTAINTYISETPOINT CALCULATION 33 pages to follow

EERlNC CONSULTANTS CALCULATION TITLE PAGE Project Client or 44 1-005 Point Beach Nuclear Station Nurn ber: Station:

Calculation Revision Total Number 2009-0001 000-A 33 Number: Number: of Pages:

Title:

Pressurizer Pressure Instrument Loop UncertaintyJSetpoint Calculation.

Original Calculation Revised Calculation Cancelled Supersedes Calculation:

SIGNATURES A m DATES CI R

A pprover: Name: Badar Hussain Signature:

Date:

ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 2 of25 REVISION

SUMMARY

SHEET Revision No. Description of the Revision 000-A This minor revision eliminates single-sided uncertainties and instead incorporates double-sided random uncertainties in the TLE term to calculate the Limiting Trip Setpoints (LTSP).

h addition, separate markups of calibration procedures (ICPs) are included in Attachment A for Current and EPU conditions.

All the changes made in this minor revision are identified by revision bars.

a f C IENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS .

Rev No: 000-A Page: 3 of 25 CALCULATION TABLE OF CONTENTS SECTION PAGE CALCULATION TITLE PAGE...............................................................................1 REVISION

SUMMARY

SHEET..............................................................................2 CALCULATION TABLE OF CONTENTS ............................................................3

1.0 BACKGROUND

. PURPOSE. AND SCOPE OF CALCULATION ...........4 2.0 ACCEPTANCE CRITEF!IA.........................................................................4 3.0 ABBREVIATIONS ......................................................................................4

4.0 REFERENCES

.............................................................................................4 5.0 ASSUMPTIONS ..........................................................................................-5 6.0 DESIGN INPUTS .........................................................................................5 7.0 METHODOLOGY .......................................................................................5 8.0 BODY OF CALCULATION........................................................................6 9.0 RESULTS AND CONCLUSIONS. WITH LIMITATIONS ......................16 10.0 IMPACT ON PLANT DOCUMENTS ........................................................24 11.0 ATTACHMENT LIST................................................................................. 25 12.0 10CFR50.59 REVIEW ................................................................................ 25

a c i ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 4 of25

1.0 BACKGROUND

, PURPOSE, AND SCOPE OF CALCULATION 1.1 Background Same as Revision 000 of calculation 2009-0001.

1.2 Purpose Same as Revision 000 of calculation 2009-0001.

1.3 Purpose of this Minor Revision The purpose of this minor revision is to calculate the Limiting Trip Setpoints (LTSP) by applying double-sided random uncertainties to the random portion of the Total Loop Error (TLE). This resolves the concern raised in CAP 0 1173082.

1.4 Scope The scope of base calculation remains unaffected except to:

9 Determine the Limiting Trip Setpoints (LTSP) for the reactor trip and ESFAS functions taking into consideration the double-sided random uncertainties in the Total Loop Error (TLE) 1.5 Instrumentation Evaluated Same as Revision 000 of calculation 2009-0001 2.0 ACCEPTANCE CRITERIA Same as Revision 000 of calculation 2009-0001 3.0 ABBREVIATIONS Same as Revision 000 of calculation 2009-0001

4.0 REFERENCES

Same as Revision 000 of calculation 2009-0001

a c lENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 5 of 25 5.0 ASSUMPTIONS Same as Revision 000 of calculation 2009-0001.

6.0 DESIGN INPUTS Same as Revision 000 of calculation 2009-0001.

7.0 METHODOLOGY 7.1 Uncertainty Determination Same as Revision 000 of calculation 2009-0001 except for Section 7.1.5.

7.1.5 Limiting Trip Setpoint (LTSP) Equation summary The LTSP is determined by applying the Total Loop Error (TLE) to the AL or PL. The TLE consists of the combination of 95/95 double-sided random uncertainties and bias uncertainties. The TLE based on a double-sided distribution is larger than the TLE based on a single-sided distribution.

Therefore, including double-sided random uncertainties in the TLE is an acceptable, conservative deviation from the guidance in DG-I01 (Section 3.3.8.4, Reference G.l of the base calculation), which permits smaller single-sided random uncertainties.

In 2010, NRC advised Point Beach that the NRC would no longer accept the use of single-sided random uncertainties for determining Limiting Safety System Settings (LSSS) in the plant Technical Specifications. Double-sided uncertainties in the random portion of the TLE term yields a more conservative LTSP value than an LTSP based on single-sided uncertainties.

Therefore, a TLE based on double-sided uncertainties is appropriate and acceptable for LSSS values.

I For a process increasing toward the analytical limit (AL), the calculated Limiting Trip Setpoint is as follows:

LTSP?' = AL + [TLErdm-+TLEbjailPS (Eq. 7.1.5-1)

For a process decreasing from normal operation toward the analytical limit, the calculated Limiting Trip Setpoint is determined as follows:

mcI ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 6 of 25 Per Section 3.3.8.4 of Reference G.1, for backup and anticipatory trips that lack an analytical limit, the setpoint is determined by subtracting (or adding for a decreasing setpoint) the total loop error from a Process Limit (PL) established either by system design requirements or using an instrument span limit. For these functions, the calculated setpoint (SP) is as follows:

Increasing Setpoints SP? = PL + ( TLE,ai + TLEbiai )* PS (Eq. 7.1.5-3)

Decreasing Setpoints SP&= PL+ ( TLE,~,++T L E )*~ PS ~ ~ (Eq. 7.1.5-4)

Drift Considerations Same as Revision 000 of calculation 2009-0001.

Multiple Analytical Limits Considerations Same as Revision-000 of calculation 2009-0001.

Margin-to-Trip Evaluation Same as Revision 000 of calculation 2009-0001.

BODY OF CALCULATIONS Device Uncertainty Analysis Same as Revision 000 of calculation 2009-0001.

Device Uncertainty Summary Same as Revision 000 of calculation 2009-000 1.

Total Loop Errors Same as Revision 000 of calculation 2009-0001.

M f C I ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 7 of 25 8.4 Setpoint Evaluations 8.4.1 High PZR Pressure Reactor Trip Setpoint Evaluation - Current Power Level For an increasing setpoint towards the Analytical Limit, Equation 7.1.5-1 is used.

'Where:

ALH-RPS = 2410 psig Section 6.5 TLEH-wS-rdrn-= - 2.166 % span Section 8.3.1 TLEH-RP~-~ =~- 0.092

~ ~ ' % span Section 8.3.1 PS = 800 psi Section 6.9 Substituting, TLEH-~~-totaI = (-2.166% - 0.092%) = -2.258 % span LTSPH-RPS = 2391.9 psig From Section 6.5, the Field Trip Setpoint (FTSPH-rnS)for High PZR Pressure Reactor Trip is 2365.0 psig. The FTSPH-RPSis less than the calculated LTSPH-RPS. Per Section 2.0, the FTSPH-W~ is conservative and is acceptable.

Margin-to-Trip Evaluation Per Attachment E, the Margin-to-Trip should remain above the peak process parameter of 2351 psia under normal operating conditions. Using Equation 7.4-1, Margin-to-Trip = FTSP - (TLE*PS)

-2.258%*800 psi

= 2365 psig +

100%

a c i ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 8 of 25

= 2346.9 psig or 2361.6 psia Therefore, since the Margin-to-Trip (2361.6 psia) is greater than the Peak Process Parameter (2351 psia), the Field Trip Setpoint (FTSPH..ws) is acceptable.

The margin between LTSPH-rnSand FTSPH-Rpsis calculated in accordance with Section 3.3.8.5 of Reference G. 1:

Margin- LTSPH-rnS- FTSPH-rnS Where:

LTSPH-rnS = 2391.9 psig I

FTSPH-rnS = 2365.0 psig Section 6.5 Substituting, Margin= 2391.9 psig - 2365.0 psig Margin = 26.9 psi 8.4.2 High PZR Pressure Reactor Trip Setpoint Evaluation - EPU For an increasing setpoint towards the Analytical Limit, Equation 7.1.5-1 is used.

LTSPH-RPST = AL H-RPS + [TLEH-RPS-~~L TLEH-RPs-~~~~IPS Where:

&H-RPS = 2403 psig Section 6.5 TLEH-ws-rd, = - 2.166 % span Section 8.3.1 TLEH-wS-bias- = - 0.092 % span Section 8.3.1 PS = 800 psi Section 6.9 Substituting, TLE~-~ps-tota, = (-2.166% - 0.092%) = -2.258 % span

KC8 ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEiETS Rev. No: 000-A Page: 9 of 25

-2.258%*8OOpsi LTSPH-~~ = 2403 psig +

100%

LTSPH-RPS = 2384.9 psig (95195)

From Section 6.5, the Field Trip Setpoint (FTSPH-wS)for High PZR Pressure Reactor Trip is 2365.0 psig. The FTSPsRps is less than the calculated LTSPH-w ~ Per

. Section 2.0, the F T S P H - Ris~conservative

~ and is acceptable.

Margin-to-Trip Evaluation Per Attachment E, the Margin-to-Trip should remain above the peak process parameter of 235 1 psia under normal operating conditions. Using Equation 7.4-1, Margin-to-Trip = FTSP - (TLE*PS)

-2.258%*800 psi

= 2365 psig +

100%

1 = 2346.9 psig or 2361.6 psia Therefore, since the Margin-to-Trip (2361.6 psia) is greater than the Peak Process Parameter (235 1 psia), the Field Trip Setpoint ( F T S P H - ~is~ )

acceptable.

The margin between L T S P H -and ~ ~FTSPH-wSis calculated in accordance with Section 3.3.8.5 of Reference G.1:

Where:

I LTSPH-~s FTSPH-RP~

= 2384.9 psig

= 2365.0 psig Section 6.5 Substituting, I Margin= 2384.9 psig - 2365.0 psig Margin = 19.9 psi

ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 10 of 25 8.4.3 Low PZR Pressure Reactor Trip Setpoint Evaluation - Current Power Level Low PZR Pressure Reactor Trip - Dropped Rod For a decreasing setpoint towards the Analytical Limit, Equation 7.1.5-2 is used.

Where:

ALL-RPS-ROD = 1815 psig Section 6.5

+ = + 2.334 % Span Section 8.3.2 TLEL-RPS-ROD-rdm

+

TLEL-RPS-ROD-bias = + 0.000 % span Section 8.3.2 PS = 800 psi Section 6.9 Substituting, TLEL-RPS-ROD-~O~~I = (2.334% + 0.000%) = 2.334 % span 2.334%

• 8OOpsi LTSPL-RPS-ROD 4 = 1815psig+

100%

LTSPL-RPS-ROD & = 1833.7 psig (95195)

Low PZR Pressure Reactor Trip - SBLOCA For a decreasing setpoint towards the Analytical Limit, Equation 7.1.5-2 is used.

Where:

ALL-RPS-LOCA = 1648 psig Section 6.5

+ Section 8.3.3 T L E L - R P s - ~ ~ ~=A - 3.5

~ ~15

~ % span

+ = 0.000 % Span Section 8.3.3 PS = 800 psi Section 6.9 Per Section 6.7.1, the Low PZR Pressure Reactor Trip (SBLOCA) analytical limit is lower than the calibrated span of the transmitter and should be

a c i ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 11 of 25 replaced in the setpoint evaluation by the lower span limit of the transmitter.

LTSPL-RPS-LOCA'~ = 1728.1 psig (95195)

The LTSP for the Low PZR Pressure Reactor Trip is taken to be the most conservative of the LTSPs calculated above. Therefore, II LTSPL-RPS = 1833.7 psig From Section 6.5, the Field Trip Setpoint (FTSPLbRPS) for LOWPZR Pressure Reactor Trip is 1925.0 psig. The FTSPL.-~~ is greater than the calculated LTSPL-R~~. Per Section 2.1, the FTSPL-RP~ is conservative and is acceptable.

Margin-to-Trip Evaluation Per Attachment E, the Margin-to-Trip should remain below the peak process parameter of 2 136 psia under normal operating conditions. The loop uncertainty for normal environmental conditions is for the dropped rod case.

Using Equation 7.4-2, Margin-to-Trip = FTSP + (TLE*PS)

= 1925 psig + 2.334% *8OOpsi 100%

= 1943.7 psig or 1958.4 psia I Therefore, since the Margin-to-Trip (1958.4 psia) is less than the Peak Process Parameter (2136 psia), the Field Trip Setpoint (FTSPL.ws) is acceptable.

The worst-case margin between L T S P L -and ~ ~ FTSPL-wsis calculated in accordance with Section 3.33.5 of Reference G. 1, based on the dropped rod event:

Where:

I. LTSPL.rnS = 1833.7 psig

ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SKEETS Rev. No: 000-A Page: 12 of 25 FTSPL.~~ = 1925.0 psig Section 6.5 Substituting, Margin = 1925.0 psig - 1833.7psig Margin = 91.3 psi 8.4.4 Low PZ;R Pressure Reactor Trip Setpoint Evaluation - EPU Low PZR Pressure Reactor Trip - OPTOAX For a decreasing setpoint towards the Analytical Limit, Equation 7.1.5-2 is used. As discussed in Appendix E, the containment environment is normal for the accidents analyzed under OPTOAX. Therefore, the same random and bias TLE terms used for a rod drop accident LTSP calculation in 8.4.3 above are applied to this LTSP calculation.

Where:

AL L-RPS-OPTOAX = 184.0psig Section 6.5

+ = + 2.334 % span Section 8.3.2 TLEL-ws-~oD-rdm

+ = + 0.000 % Span Section 8.3.2 TLEL-RPs-RoD-~~~~

PS = 800 psi Section 6.9 Substituting, TLEL-~~-Ro~-totai = (2.334% + 0.000%) = 1.958 % span 2.334%

• 8OOpsi LTSPL-mS-OPTOAX = 1840 psig +

100%

LTSPL-RPS-OPTOAX = 1858.7 psig (95195)

The LTSP for the Low PZR Pressure Reactor Trip for Extended Power Uprate is the LTSP calculated above. Therefore, LTSPL-R~~ = 1858.7 psig From Section 6.5, the Field Trip Setpoint (FTSPL-wS)for LOWPZR Pressure Reactor Trip is 1925.0 psig. The FTSPL-wsis greater than the calculated

%ca ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 13 of 25 LTSPL-rnS.Per Section 2.1, the FTSPL-rnSis conservative and is acceptable.

Marpin-to-Trip Evaluation Per Attachment E, the Margin-to-Trip should remain below the peak process parameter of 2 136 psia under normal operating conditions. The loop uncertainty for normal environmental conditions is for the dropped rod case.

Using Equation 7.4-2, Margin-to-Trip = FTSP + (TLE*PS) 2.334%

• 8OOpsi

= 1925 psig +

100%

I = 1943.7 psig or 1958.4 psia 1 Therefore, since the Margin-to-Trip (1958.4 psist-)is less than the Peak Process Parameter (2136 psia), the Field Trip Setpoint (FTSPL-rnS)is acceptable.

The worst-case margin between LTSPL-rnSand FTSPL-rnSis calculated in accordance with Section 3.3.8.5 of Reference G.1, based on the dropped rod event:

Where:

I LTSPL-~s FTSPL-rnS

= 1858.7 psig

= 1925.0 psig Section 6.5 Substituting, I Margin= 1925.0 psig - 1858.7psig Margin = 66.3 psi

ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SI-FEETS Rev. No: 000-A Page: 14 of 25 8.4.5 Low PZR Pressure SI Actuation Setpoint Evaluation For a decreasing setpoint towards the Analytical Limit, Equation 7.1.5-2 is used.

Where:

ALL-SI = 1625 psig or 1648 psig Section 6.5

+ = 3.406 % span Section 8.3.4

+

TLEL-SI-bias = + 0.000 % span Section 8.3.4 PS = 800 psi Section 6.9 Per Section 6.7.3, the SI Actuation analytical limit is lower than the lower span limit of the transmitter and should be replaced in the setpoint evaluation by the lower span limit.

LTSPL-SIJ = 1727.2 psig (95195)

From Section 6.5, the Field Trip Setpoint (FTSPL-~I) for Low PZR Pressure SI Actuation is 1735.0 psig. The FTSPL-SIis greater than the calculated LTSPL-s1.

Per Section 2.1, the FTSPL-sIis conservative and is acceptable.

Per Attachment E and Section 2.3, the Low PZR Pressure SI Actuation FTSP must be no lower than 1715 psig. The FTSP is 1735.0 psig, which is greater than 1715 psig, and therefore, acceptable.

The worst-case margin between LTSPL-sIand FTSPL-sIis calculated in accordance with Section 3.3.8.5 of Reference G. 1:

Where:

I LTSPL-sI FTSPL.sI

= 1727.2 psig

= 1735.0 psig Section 6.5

ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SI-FEETS Rev. No: 000-A Page: 15 of 25 Substituting, Margin = 1735.0 psig - 1727.2 psig Margin = 7.8 psi 8.4.6 PZR Pressure SI Unblock Setpoint Evaluation (Proposed Setpoint)

Same as Revision 000 of calculation 2009-0001.

8.4.7 PZR Pressure SI Block Setpoint Evaluation (Proposed Setpoint)

Same as Revision 000 of calculation 2009-0001.

8.5 Operability Limit Determination 8.5.1 High PZR Pressure Reactor Trip Operability Limit Changes in this section are indicated by a revision bar shown below.

From Section 8.4.2, the post EPU Limiting Trip Setpoint for the high Pressurizer Pressure Reactor Trip is 2384.9 psig. For this increasing trip, the OL' value of 2370 psig is more conservative (i.e., restrictive) than the LTSP.

Per Section 2.4, the OL' value is acceptable to use for channel operability determination during COT.

8.5.2 Low PZR Pressure Reactor Trip Operability Limit Changes in this section are indicated by a revision bar shown below.

From Section 8.4.4, the post EPU Limiting Trip Setpoint for the low Pressurizer Pressure Reactor Trip is 1858.7 psig. For this decreasing trip, the OL- value of 1920 psig is more conservative (i.e., restrictive) than the LTSP.

Per Section 2.4, the OL- value is acceptable to use for channel operability determination during COT.

8.5.3 Low PZR Pressure SI Actuation Operability Limit Changes in this section are indicated by a revision bar shown below.

From Section 8.4.5, the Limiting Trip Setpoint for the low Pressurizer Pressure SI Actuation is 1727.2 psig. For this decreasing trip, the OL- value of 1730 psig is more conservative (i.e., restrictive) than the LTSP. Per Section 2.4, the OL- value is acceptable to use for channel operability determination during COT.

36Cfl ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 16 of 25 PZR Pressure SI Unblock: Operability Limit (Existing)

Same as Revision 000 of calculation 2009-0001.

PZR Pressure SI Unblock Operability Limit (Proposed)

Same as Revision 000 of calculation 2009-0001.

Acceptable As-Left and As-Found Calibration Tolerances Same as Revision 000 of calculation 2009-000 1.

Channel Check Tolerances Same as Revision 000 of calculation 2009-0001.

Scaling Same as Revision 000 of calculation 2009-0001.

R_1ESULTSAND CONCLUSIONS, WITH LIMITATIONS Analytical Limits (AL)

Same as Revision 000 of calculation 2009-0001.

Limiting Trip Setpoints, Operability Limits (OL), and Recommended Tech Spec Changes Changes in this section are indicated by a revision bar shown below.

To make the Technical Specification Allowable Values easier to remember, it is recommended that the LTSP values be rounded (in the conservative direction) to the nearest 5 psig. For example, the LTSP for the high pressurizer pressure reactor trip for EPU is 2384.9 psig. For use in Technical Specification 3.3.1, the Allowable Value should be rounded down to 2380 psig.

a c iENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 17 of 25 9.3 Calculated Limiting Trip Setpoints (LTSP) and Existing Field Trip Setpoints (FTSP)

Changes in this section are indicated by a revision bar shown below.

Table 9.3-1 Calculated Limiting Trip SetpointsIExistingField Trip Setpoints Extended Power Level For the High PZR Pressure Reactor Trip and the Low PZR Pressure Reactor Trip, the Margin-to-Trip values (>2361.6 psia and 4958.4 psia, respectively) are conservative with respect to the peak process parameter values (>2351 psia and <2136 psia, respectively), per Sections 8.4.1 and 8.4.3. Therefore, the existing FTSPs for these functions may be retained.

Revision 0 of this calculation also , , . - I t i changes to the existing Field Trip Setpoints (FTSP) for the PZR Pressure SI Block Enable and SI Unblock functions, to return these two setpoints to the correct values for an RCS operating pressure of 2250 psia, as follows:

%CI ENGINEERTNG CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 18 of 25 Table 9.3-2 Recommended Field Trip Setpoint Changes 9.4 Tech Spec Surveillance Same as Revision 000 of calculation 2009-0001.

9.5 Channel Check Tolerances Same as Revision 000 of calculation 2009-0001.

9.6 Acceptable As-Left and As-found Tolerances Same as Revision 000 of calculation 2009-0001.

9.7 Scaling Same as Revision 000 of calculation 2009-0001.

9.8 Limitations Same as Revision 000 of calculation 2009-0001.

9.9 Graphical Representation of Setpoint Parameters Changes in figures 9.9.la, 9.9.lb, 9.9.24 9.9.2b, and 9.9.3 have been indicated by a revision bar shown below, which needs to be incorporated in the next major revision. .

ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 19 of 25 9.9.1 High PZR Pressure Reactor Trip Setpoint Figure 9.9.la High PZR Pressure Reactor Trip Function - Current Power Level (PC-429A, 430A, 43 1A)

Analytical Limit (ALH-WS) 2410 psig [2425 psia]

Limiting Trip Setpoint (LTSPH-mS) 2391.9 psig

+Operability Limit (oL') 2370 psig (0.4350 Vdc)

+As-Found Tolerance (AFTaRps) 2369.4 psig (0.4347 Vdc)

+As-Left Tolerance (ALTH-RPS) 2369 psig (0.4345 Vdc)

Field Trip Setpoint (FTSPH-mS) 2365 psig (0.4325 Vdc)

-As-Left Tolerance (ALTH-WS) 2361 psig (0.4305 Vdc)

-As-Found Tolerance (AFTH-US) 2360.6 psig (0.4303 Vdc)

-Operability Limit (OL-) 2360 psig (0.4300 Vdc)

Margin-to-Trip 2346.9 psig [2361.6 psia]

Peak Process Parameter 2336.3 psig [2351 psia]

Process

ack!ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 20 of 25 Figure 9.9.lb High PZR Pressure Reactor Trip Function - EPU (PC-429A, 430A, 43 1A)

Analytical Limit (ALN-WS) 2403 psig 12418 psia]

Limiting Trip Setpoint (LTSPH-WS) 2384.9 psig

+Operability Limit ( O L ~ 2370 psig (0.4350 Vdc)

+As-Found Tolerance (AIFTH-WS) 2369.4 psig (0.4347 Vdc)

+As-Left Tolerance (ALTKws) 2369 psig (0434-5-Vdc)

Field Trip Setpoint (FTSPH-WS) 2365 psig (0.4325 Vdc)

-As-Left Tolerance (ALTH-WS) 2361 psig (0.4305 Vdc)

-As-Found Tolerance (AIFTH-WS) 2360.6 psig (0.4303 Vdc)

-Operability Limit (OL-) 2360 psig (0.4300 Vdc) 2346.9 psig [2361.6 psia]

Peak Process Parameter 2336.3 psig [2351 psia]

Process

($gcuENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION S B E T S Rev. No: 000-A Page: 21 of 25 9.9.2 Low PZR Pressure Reactor Trip Setpoint Figure 9.9.2a Low PZR Pressure Reactor Trip Bistable - Current Power Level (PC-429E, 430H, 43 15,449A)

Process Peak Process Parameter 2121.3 psig [2136 psia]

1943.7 psig [1958.4 psia]

+Operability Limit ( O L ~ 1930 psig (0.2150 Vdc)

+As-Found Tolerance (AFTL-WS) 1929.4 psig (0.2147 Vdc)

+As-Left Tolerance (ALTL-WS) 1929 psig (0.2145 Vdc)

Field Trip Setpoint (FTSPL--s) 1925 psig (0.2125 Vdc)

-As-Left Tolerance (ALTL-WS) 1921 psig (0.2105 Vdc)

-As-Found Tolerance (AFTL-WS) 1920.6 psig (0.2103 Vdc)

-Operability Liinit (OL') 1920 psig (0.2100 Vdc)

I Limiting Trip Setpoint (LTSPL-WS) 1833.7psig Analytical Limit ( A L L - ~ ~ - R O D ) 1815 psig E1829.7 psia]

1 Limiting Trip Setpoint ( L T S P L - ~ S - ~ ~ ~ ~ ) 1728.1.psig Setpoint Evaluation Starting Limit 1700 psig Analytical Limit (ALL-w~-LocA) 1648.0 psig

%cg ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 22 of 25 Figure 9.9.2b Low PZR Pressure Reactor Trip Bistable - EPU (PC-429E, 430H, 43 1J, 449A)

Process Peak Process Parameter 2121.3 psig 12136 psia]

1943.7 psig [1958.4 psia]

+Operability Liinit ( O L ~ 1930psig (0.2150Vdc)

+As-Found Tolerance (AFTL-rns) 1929.4 psig (0.2 147 Vdc)

+As-Left Tolerance (ALTL-ws) 1929 psig (0.2 145 Vdc)

Field Trip Setpoint (FTSPL-RPS) 1925 psig (0.2125 Vdc)

-As-Left Tolerance (ALTLwWS) 1921 psig (0.2105 Vdc)

-As-Found Tolerance (AFTL-RPS) 1920.6 psig (0.2 103 Vdc)

-Operability Limit (OL-) 1920 psig (0.2100 Vdc)

Limiting Trip Setpoint (LTSPL-WS) 1858.7 psig Analytical Limit ( A L L - ~ s - ~ T ~ o A x ) 1840 psig [1854.7 psia]

a c p ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 23 of 25 9.9.3 Low PZR Pressure SI Actuation Setpoint Figure 9.9.3 Low PZR Pressure SI Actuation Bistable (PC-429C, 430E, 431G)

Process

+Operability Limit ( O L ~ 1740 psig (0.1200 Vdc)

+As-Found Tolerance (AFTL-sl) 1739.4 psig (0.1 197 Vdc)

+As-heft Tolerance (ALTL-sS 1739 psig (0.1 195 Vdc)

Field Trip Setpoint (FTSPL-sl) 1735 psig (0.1 175 Vdc)

-As-Left Tolerance (ALTL-sI) 1731 psig (0.1 155 Vdc)

-As-Found Tolerance (AFTL-SI) 1730.6 psig (0.1 153 Vdc)

-Operability Limit (OL-) 1730 psig (0.1 150 Vdc)

Limiting Trip Setpoint (LTSPL-SI) 1727.2 psig [1741.9 psia]

Transmitter Minimum Range Limit 1700 psig [I 7 14.7 psia]

Analytical Limit (ALL-SI -sLB) 1648.3 psig [I663 psia]

Analytical Limit (ALL..SI - L O C ~ ) 1625 psig [1639.7 psia]

KC8 ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 24 of 25 10.0 IMPACT ON PLANT DOCUMENTS As a result of this minor revision, the following plant documents should be revised as follows:

IICP 02.001RD, "Reactor Protection and Engineered Safety Features Red Channel Analog 92 Day Surveillance Testy'(See Attachment A for changes).

21CP 02.001RD, "Reactor Protection and Engineered Safety Features Red Channel Analog 92 Day Surveillance Test" (See Attachment A for changes).

IICP 02.001BL' "Reactor Protection and Engineered Safety Features Blue Channel Analog 92 Day Surveillance Testy'(See Attachment A for changes).

21CP 02.001BLY"Reactor Protection and Engineered Safety Features Blue Channel Analog 92 Day Surveillance Test" (See Attachment A for changes).

IICP 02.001WH, "Reactor Protection and Engineered Safety Features White Channel Analog 92 Day Surveillance Test (See Attachment A for changes).

21CP 02.001WHY"Reactor Protection and Engineered Safety Features White Channel Analog 92 Day Surveillance Test" (See Attachment A for changes).

1ICP-02.001YLY"Reactor Protection and Engineered Safety Features Yellow Channel Analog 92 Day Surveillance Test" (See Attachment A for changes).

21CP 02.001YL,, Rev. 13, "Reactor Protection and Engineered Safety Features Yellow Channel Analog 92 Day Surveillance Test" (See Attachment A for changes).

IICP 02.020RDY"Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes).

21CP 02.020RD' "Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes).

IICP 02.020BLY"Post-Refueling Pre-Startup RPS and ESF Blue Channel Analog Surveillance Test" (See Attachment A for changes).

21CP 02.020BL' "Post-Refueling Pre-Startup RPS and ESF Blue Channel Analog Surveillance Test" (See Attachment A for changes).

IICP 02.020WHY"Post-Refueling Pre-Startup RPS and ESF White Channel Analog Surveillance Test" (See Attachment A for changes).

21CP 02.020WHY"Post-Refueling Pre-Startup RPS and ESF White Channel Analog Surveillance Testy'(See Attachment A for changes).

IICP 02.020YLY"Post-Refueling Pre-Startup RPS and ESF Yellow Channel Analog Surveillance Testy'(See Attachment A for changes).

21CP 02.020YL' "Post-Refueling Pre-Startup RPS and ESF Yellow Channel Analog Surveillance Test" (See Attachment A for changes).

mc! ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: 25 of 25 II 0 Tech Spec 3.3.1, Table 3.3.1-1, Functions 7.a and 7.b After EPU license amendment 261 is approved to make the change, revise the "Pressurizer Pressure - Low" and "Pressurizer Pressure - High" reactor trip I Allowable Values to 2 1860 psig and 1.2380 psig, respectively, and eliminate Notes (h) and (i) in Table 3.3.1-1.

I Tech Spec 3.3.2, Table 3.3.2-1, Function Id.

After EPU license amendment 261 is approved to make the change, revise the Safety Injection'- Pressurizer Pressure Low Allowable Value froin 2 1715 psig to 2 1730 psig.

I 0 Tech Spec 3.3.2, Table 3.3.2-1, Function 8 After EPU license amendment 261 is approved to make the change, revise the "SI Unblock - Pressurizer Pressure" Allowable Value from 1. 1800 psig to 1.2005 psig.

DBD-25 Section A, Revision 3, Figure A.2.2-1 needs to be revised to change the High and Low Pressurizer Pressure Reactor Trip Tech Spec Values to their post-EPU values.

e DBD-27 Revision 5, Table 2-2 needs to be revised to change the High and Low Pressurizer Pressure Reactor Trip Tech Spec Values to their post-EPU values.

11.0 ATTACHMENT LIST Same as Revision 000 of calculation 2009-0001 except for Attachment A.

Revised pages A3, A4, A5 and A6. Added pages A7, A8, A9 and A10. Re-numbered page A7 (original) to A 11.

12.0 10CFR 50.59 REVIEW Same as Revision 000 of calculation 2009-000 1. No separate 10CFR50.59 screening is required as a result of this minor revision.

ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: A1 ofA8 ATTACHMENT A Page A31 I Section 5.18.1 of l(2) ICP 02.001BL (Ref. P.2 and P.7) and Section 5.12.1 of l(2) ICP 02.020BL (Ref. P.24 and P.281, [CURRENT1

• cg ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: A2 of A8 ATTACKMENT A (Page A4) 1 Section 5.18.1 of 1(2) ICP 02.001R.D (Ref. P.3 and P.8) and Section 5.13.1 of 1(21 ICP 02.020R.D (Ref. P.25 andP.29). lCURRENTl

a C 1ENGINI~EF~NG CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: A3 of A8 ATTACHMENT A (Page AS)

I Section 5.18.1 of l(2) ICP 02.001WH (Ref. P.4 and P.9) and Section 5.12.1 of l(2) ICP 02.020WH (Ref. P.26 and P.30). rCURRENTl

-$=I ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: A4 ofA8 ATTACHMENT A (Page A6)

I Section 5.16.1 of l(2) ICP 02.001YL (Ref. P.5 and P.10) and Section 5.1 1.1 of l(2) ICP 02.020YL (Ref. P.27 and P.3 1). lCURRENTl Pressurizer Pressure Low Pressurizer Trip Function Technical Specification Limit l(2)-PC-449A 2 0.1675 Vdc (2 1835 psig) (Ref: Calculation 2009-0001 Rev. 0 )

ENGINEEFSNG CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: A5 of A8 ATTACHMENT A (Page A7)

/ Section 5.18.1 of l(2) ICP 02.001BL (Ref. P.2 andP.7) and Section 5.12.1 of l(2) ICP 02.02OBL (Ref. P.24 andP.28). rEPUl Pressurizer Pressure

aCBI ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: A6 ofA8 ATTACHMENT A (Page A8)

Section 5.18.1 of l(2) ICP 02.001RD (Ref. P.3 and P.8) and Section 5.13.1 of l(2) ICP 02.020RD (Ref. P.25 and P.29). lEPUl

.Low PZR Pressure Trip Function Technical Specification Limit l(2)-PC-429E t 0.1800 Vdc (2 1860 psig) (Ref: Calculation 2009-0001 Rev 0)

ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: A7 of A8 ATTACHMENT A (Page A9)

Pressurizer Pressure

- Unblock SI Function Technical Specification Limit l(2)-PC-430F 10.2525 Vdc (I2005psig) (Ref: Calculation 2009-0001 Rev OA)

a c I ENGINEERING CONSULTANTS Calculation No: 2009-0001 CALCULATION SHEETS Rev. No: 000-A Page: A8 of A8 Attachment A (Page A10)

I Section 5.16.1 of l(2) ICP 02.00112 (Ref. P.5 andP.10) and Section 5.11.1 of 1 (2) ICP 02.020YL (Ref. P.27andP.31). lEPw Pressurizer Pressure e Low Pressurizer Trip Function Technical Specification Limit, l(2)-PC-449A t 0.1800 Vdc ( 2 1860 psig ) (Ref: Calculation 2009-0001 Rev. 0 )

ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 261, EXTENDED POWER UPRATE TRANSMIlTAL OF SAMPLE CALCULATIONS FOR REACTOR PROTECTION SYSTEM IENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SETPOINT CALCUATIONS POWER RANGE NUCLEAR INSTRUMENTATION UNCERTAINTYISETPOINT CALCULATION 19 pages follow

ENGINEERING CONSULTANTS CUCmATIEON TI[TEE PAGE Project Client or 441-005 Point Beach Nuclear Station Number: Station:

Calculation Revision Total Number 2009-0002 000-A 19 Number: Number: of Pages:

Title:

Power Range Nuclear Instrumentation UncertaintylSetpoint Calculation

[7 Original Calculation Revised Calculation [7 Cancelled

[7 Supersedes Calculation:

Nuclear Safety Related:

Kb'Es KIN0 QA Scope: BYES rho System: IIPP Date of Issue: See Approval Date SIGNATmES AND DATES Preparer Reviewer Discipline Name Signatye Date El I&C Aijaz A h e d .e&L&/>Y/Q h

• I&C Saravanan Makayee h./-\ --C-6/ 2 ~ / 1 0 Approver: Name: Badar Httssain Signature:

Date:

wc! ENGINEERING CONSULTANTS CaIcuIation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 2 of 17 REVISION SUlWMARY SHEET Revision No. Description of the Revision 000-A This minor revision incorporates double sided random uncertainties to calculate Limiting Trip Setpoints (LTSP) and revises Field Trip Setpoint (FTSP) for the High Range - High Flux Reactor Trip Setpoint for the EPU condition.

All the alpha-numeric changes in this minor revision are marked up revision bars.

a C U ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev.No: 000-A Page: 3 of 17 CALCULATION TABLE OF CONTENTS SECTION PAGE CALCULATION TITLE PAGE ...........................................................................1 REVISION SlJMMAR.YSHEET .......................................................................... 2 CALCULATION TABLE OF CONTENTS ........................................................3 1.0 PURPOSE .......................................................................................................4 2.0 ACCEPTANCE CRITERIA......................................................................... 4 3.0 ABBREVIATIONS ........................................................................................ 4

4.0 REFERENCES

.............................................................................................. 4 5.0 ASSUMPTIONS ............................................................................................ 4 6.0 DESIGN INPUTS .......................................................................................... 4 7.0 METHODOLOGY ........................................................................................4 8.0 BODY OF CALCULATION ........................................................................ 5 9.0 RESULTS AND CONCLUSIONS..............................................................10 10.0 IMPACT ON PLANT DOCUMENTS........................................................16 11.0 ATTACHMENT LIST .........................................i ....................................... 17 12.0 10CFR50.59 REVIEW..................................................................................17

W C i ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 4 of 17 1.0 PURPOSE The purpose of this minor revision is to calculate the Limiting Trip Setpoint (LTSP) for the HighlLow - Range - High Flux Reactor Trip Setpoint by applying double sided random uncertainties to the random portion of the Total Loop Error (TLE). This resolves the concern in CAP 01 173082.

In addition, as a result of calculating the LTSP for the High Range - High Flux Reactor Trip for EPU, this minor revision also recommends changing the EPU Field Trip Setpoint (FTSP), to avoid the FTSP as-found tolerance from overlapping the LTSP (and corresponding TS Allowable Value). This will allow the LTSP to be rounded to the new TS Allowable Value without the normal as-found tolerance for the field setpoint violating the TS AV.

2.0 ACCEPTANCE CRITERIA Same as Revision 0 of Calculation 2009-0002.

3.0 ABBREVIATIONS Same as Revision 0 of Calculation 2009-0002.

4.0 REFERENCES

Same as Revision 0 of Calculation 2009-0002.

5.0 ASSUMPTIONS Same as Revision 0 of Calculation 2009-0002.

6.0 DESIGN INPUTS Same as Revision 0 of Calculation 2009-0002.

7.0 METHODOLOGY Same as Revision 0 of Calculation 2009-0002 except for section 7.2.

7.2 Limiting Trip Setpoint (LTSP) Equation Summary For setpoints that are based on an Analytical Limit (AL) or Process Limit (PL), a Limiting Trip Setpoint (LTSP) shall be calculated. The LTSP represents the most limiting value a channel trip setpoint can have that will ensure the AL or PL is not exceeded, considering all credible instrument channel errors that can exist between successive calibrations. The LTSP provides the basis for establishing an Allowable Value (AV) in the Technical Specifications.

%ca ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 5 of 17 The LTSP is determined by applying the Total Loop Error (TLE) to the AL or PL.

The TLE consists of the combination of 95/95 double-sided random uncertainties and bias uncertainties. The uncertainty value associate with the double-sided distributions is larger than the value associated with the single-sided distributions. Therefore, including double-sided random uncertainties in the TLE is an acceptable, conservative deviation fiom the guidance in DG-I01 (Reference G. l), which permits smaller single-sided random uncertainties. In 2010, NRC advised Point Beach that the NRC would no longer accept the use of single-sided random uncertainties for determining Limiting Safety System Settings (LSSS) in the plant Technical Specifications. Double-sided uncertainties in the random portion of the TLE tern yields a more conservative LTSP value than an LTSP based on single-sided uncertainties. Therefore, a TLE based on double-sided uncertainties is appropriate and acceptable for LSSS values.

Consistent with the methodology of Reference G. 1, random and bias portions of the TLE are calculated separately and are then combined using an appropriate sign convention based on the direction that the process variable approaches the setpoint.

For a process variable increasing toward the AL (or PL), the calculated LTSP is as follows:

LTSPT = AL+ [ TLErdm- + TLEbiai ]*PS (Eq. 7.2-1)

For a process variable decreasing towards the AL (or PL), the calculated LTSP is as follows BODY OF CALCULATIONS Sections, 8.1, 8.2, and 8.3 of the base calculation pertaining to Device Uncertainty Analysis, Device Uncertainty Suninary, and Total Loop Errors are not affected by this minor revision.

ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 6 of 17 8.4 Setpoint Evaluations 8.4.1 Power Range High Range High Flux Reactor Trip Setpoint Evaluation -

Current Power Level I For an increasing setpoint towards the Analytical Limit, Eq. 7.2-1 is used.

where, AL = 118% RTP Section 6.5 TLETRIpqdm-= -6.342% Span Section 8.3.1 TLETRp-bias-= 0.000% Span Section 8.3.1 PS = 120% RTP I Substituting, L T S P H ~ 118%

= RTP + [-6.342% span+ 0.000% span]*l20% RTP L T S P H=~ 110.4% RTP (95195)

The margin between LTSP and FTSP is calculated as follows:

Margin= LTSP - FTSP I where, LTSP = 110.4% RTP FTSP = 107% RTP Section 6.5 Substituting, Margin= 110.4% RTP - 107% RTP Margin = 3.4% RTP 8.4.2 Power Range High Range High Flux Reactor Trip Setpoint Evaluation - EPU For an increasing setpoint towards the Analytical Limit, Eq. 7.2-1 is used.

where, ALEPU = 116%RTP Section 6.5 T L E T ~ ~= --6.342%

~ ~ ~ -span Section 8.3.1

a c l ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 7 of 17 TLE~m-biai= 0.000% span Section 8.3.1 PS = 120% RTP Substituting, LTSPm = 116% RTP + [-6.342% span+ 0.000% span]" 120% RTP LTSPm= 108.4% RTP (95195)

From Section 6.5, the existing Field Trip Setpoint (FTSP) for High Range High Flux Reactor Trip Setpoint is 107% RTP. The existing FTSP value is conservative to the calculated LTSP value of 108.4% RTP; however, the upper As-Found value for an FTSP of 107% RTP would overlap the LTSP, making the LTSP unusable as the basis for the TS Allowable Value. Therefore, to prevent overlap between the new LTSP and the FTSP as-found tolerance, a lower FTSP of 106% RTP is recommended for EPU to meet the acceptance criteria outlined in Section 2.2 of the base calculation and to allow using the LTSP as the basis for the EPU TS Allowable Value.

The margin between LTSP and the recommended FTSP is calculated as follows:

Margin= LTSP - FTSP where, LTSP = 108.4% RTP FTSP = 106% RTP (Recommended FTSP)

Substituting, Margin = 108.4% RTP - 106% RTP Margin = 2.4% RTP Power Range Low Range High Flux Reactor Trip Setpoint Evaluation (For both Current Power Level and EPU)

For an increasing setpoint towards the Analytical Limit, Eq. 7.2-1 is used.

where, AL = 35% RTP Section 6.5 TLETRIPqdm- = -6.342% span Section 8.3.1 T L E T ~ -=~0.000%

~ ~ ~ span

- Section 8.3.1

a c i ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 8 of 17 PS = 120% RTP Substituting, I LTSPLR = 35% RTP + [-6.342% span+ 0.000% span]*l20% RTP LTSPLR= 27.4% RTP (95195)

The margin between LTSP and FTSP is calculated as follows:

Margin = LTSP - FTSP where, LTSP = 27.4% RTP FTSP = 20% RTP Section 6.5 Substituting, Margin = 27.4% RTP - 20% RTP I1 Margin = 7.4% RTP 8.4.4 Permissive Setpoint Evaluation The Permissive Setpoint Evaluation performed in the base calculation is not affected by this minor revision.

8.5 Operability Limit Determination Same as Revision 0 of Calculation 2009-0002, except for sections 8.5.1 and 8.5.2.

8.5.1.1 High Range - High Flux Reactor Trip Operability Limit - Current Power Level Same as Revision 0 of Calculation 2009-0002, except for following changes:

From Section 8.4.1, the Limiting Trip Setpoint for the High Range - High Flux I Reactor Trip is 110.4% RTP. For this increasing trip, the OL+value of 110% is more conservative (i.e., restrictive) than the LTSP. Per Section 2.2, with margin between the OL+value and the LTSP, the OL' value is acceptable to use for channel operability determination during COT.

a C B ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 9 of 17 8.5.1.2 High Range - E g h Flux Reactor Trip Operability Limit - EPU Using Equation 7.1.5-3 to determine the COT 30 drift value, Rds, = (1.5) Rd2, (Eq. 7.1.5-3)

Rd3, = (1.5) 2.0 % span (Dd2, fiom Section 8.1.1 1)

Rd3, =

• 3.0 %span The recommended FTSP for the high range - high flux trip of 106% (Section 8.4.2),

expressed as percent span, is:

FTSP = 106 + 120% = 88.33 % span Using Equation 7.1.5-1, the OL' is determined as:

OL' = FTSP + [RAL~+ ~dg:]" (Eq. 7.1.5-1)

OL+ = 88.33 % + (0.833~+ 3.0~)" (RAL is Dv2 fiorn Section 8.1.13)

OL' = 88.33 % + 3.11 OL' = 91.44 % span Expressed in % RTP, OL' = (0.9144

• 120%) = 109.72%

Note that the OL+value calculated above for the recommended FTSP of 106% RTP is greater than the LTSP value of 108.4 % RTP calculated in section 8.4.2. The LTSP will be conservatively rounded down to determine the TS Allowable Value.

Because the TS AV must be used to determine operability of the channel when the calculated OL' exceeds the LTSP, a default 0L'value to be used in the calibration procedures will be the TS AV, rather than the larger calculated OL+.

For readability in the calibration procedures, the default OL+will be conservatively rounded down to the nearest whole percent. Therefore, the default OL' = 108%.

Using Equation 7.1.5-2, the OL- is determined as:

(

I OL- = FTSP - [RAL~+ ~d3:l" (Eq. 7.1.5-2)

OL- = 88.33 % - (0.833~+ 3.0~)"

OL- = 88.33 % - 3.11 OL- = 85.22 % span Expressed in % RTP, OL- = (0.8522

• 120%) = 102.26%

a c 8 ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 10 of 17 For readability in the calibration procedures, the OL- is conservatively rounded up to the nearest whole percent. Therefore, OL- = 103%.

Because the High Range - High Flux Reactor Trip is an increasing trip, the OL' value of 108% should be the limit compared to the COT as-found value to determine Technical Specification operability of the channel. However, an as-found value outside either the OL' or OL- indicates that the channel is operating abnormally.

8.5.2 Low Range - High Flux Reactor Trip Operability Limit Same as Revision 0 of Calculation 2009-0002, except for following changes:

From Section 8.4.3, the Limiting Trip Setpoint for the Low Range - High Flux 1 Reactor Trip is 27.4% RTP. For this increasing trip, the OL' value of 23% is more conservative (is., restrictive) than the LTSP. Per Section 2.2, with margin between the OL' value and the LTSP, the OL' value is acceptable to use for channel operability determination during COT.

9.0 RESULTS AND CONCLUSIONS WITH LIMITATIONS 9.1 Total Loop Error Same as Revision 0 of Calculation 2009-0002.

9.2 Analytical Limits Same as Revision 0 of Calculation 2009-0002.

ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SI-EEETS Rev. No: 000-A Page: 11 of 17 9.3 Limiting Trip Setpoints, Operability Limits (OL), and Recommended Tech Spec Changes Same as Revision 0 of Calculation 2009-0002, except Table 9.3-1 Table 9.3-1 OperabiIity Limits

W C ! ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 12 of 1'7 9.4 Set Point Evaluation I Same as Revision 0 of Calculation 2009-0002, except Table 9.4.1 Table 9.4.1, Trip Setpoints High-Range - 106%? RTP Section High Flux Trip @. 108.4% RTP 5 108% RTP 2.4% RTP (Recommended) .8.4.2 EPU level Low Range - Section 27.4% RTP 5 27% RTP 20%? RTP 7.4% RTP High Flux Trip 8.4.3 Rod Withdrawal Section N/A N/A l05%? RTP N/A Stop 8.4.5 9.5 Acceptable As-Left and As-Found Tolerances Same as Revision 0 of Calculation 2009-0002.

9.6 Channel Check Tolerance Same as Revision 0 of Calculation 2009-0002.

9.7 Limitations Same as Revision 0 of Calculation 2009-0002.

acc&gENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 13 of 17 9.8 Graphical Representation of Setpoints Same as Revision 0 of Calculation 2009-0002, except for Figures 9.8.1,9.8.2, and 9.8.3.

Figure 9.8.1, High Range - High Flux Reactor Trip Setpoint for Current Power Level Analytical Limit LTSP 110.4% RTP Allowable Value (proposed)/ OL+ 110% RTP As-Found +

As-Left +

t 109% RTP 108% RTP FTSP 1 107% RTP As-Left- 106% RTP i 105% RTP T

104% RTP

ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 14 of 17 Figure 9.8.2, High Range - High Flux Reactor Trip Setpoint for Extended Power Uprate Analytical Limit LTSP, 116% RTP 108.4% RTP AIIowable Value (proposed)/ 108% RTP OL+ /As-Found+

As-Left+ 107% RTP FTSP 106% RTP

-I--

As-Left- 105% RTP As-Found-OL-I 103% RTP

ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 15 of 17

+

Figure 9.8.3, Low Range - mgh Flux Reactor Trip Setpoint Analytical Limit 35% RTP LTSP 27.4% RTP Allowable Value (proposed) 27% RTP 23% RTP As-Found + 22% RTP As-Left + 21% RTP FTSP 20% RTP As-Left- 19% RTP AS-Found- 18% RTP

-+- 17% RTP

awcllENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 16 of 17 10.0 IMPACT ON PLANT DOCUMENTS The following Plant documents are affected by this minor revision.

o Setpoint Document, STPT 1.1, "Reactor Trip NIS, Unit 1" For EPU, the High Range -High Flux setpoint should be changed per Section 9.4.

o Setpoint Document, STPT 1.1, "Reactor Trip NIS, Unit 2" For EPU, the High Range - High Flux setpoint should be changed per Section 9.4.

When EPU License Amendment 261 is approved, the following six ICPs need to be revised to incorporate the new EPU values for the TS Allowable Values, the new FTSP for the High Range - High Flux bistables for loops N-41 through N-44, and the corresponding as-left and as-found tolerances and Operability Limits. See Attachment B for ~narltedup ICP data sheet changes.

B lICP 02.007, "Nuclear Instmentation Power Range Channels 92 Day Channel Operational Test" (See Attachment B for changes).

21CP 02.007, "Nuclear Instrumentation Power Range Channels 92 Day Channel Operational Test" (See Attachment-B-for changes).

e lICP 02.022, "Nuclear Instrunentation System Power Range Channels Shutdown operational Test" (See Attachment B for changes).

e 21CP 02.022, "Nuclear Instrumentation System Power Range Channels Shutdown operational Test" (See Attachment B for changes).

e lICP 02.008-3, "Nuclear Instrumentation Power Range Channels Overpower Trip High Range Adjustment" e 2ICP 02.008-3, "Nuclear Instrumentation Power Range Channels Overpower Trip High Range Adjustment" Technical Specification 3.3.1 "Reactor Protection System (RPS) Instrumentation" Table 3.3.1-1 Functions 2.a and 2.b.

When EPU License Amendment 26 1 is approved, new Allowable Values for Low Range -High Flw, High Range - High Flux determined in this calculation should be incorporated in Table 3.3.1-1.

~~~ ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: 17 of 17 11.0 ATTACHMENT LIST Same as Revision 0 of Calculation 2009-0002, except Attachment B. See the attached pages for the changes in Attachment B.

12.0 10CFR 50.59 REVIEW IOCFR 50.59 screening SCR 2007-0078-00 performed for the base calculation is also applicable to this minor revision. Therefore, no additional 50.59 screening is required.

ENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: B1 of B2 Attachment B Changes to Attachment B are as follows:

l(2) ICP 02.007 Series - Current Power Level New limits for N-41 Red Channel I, N-42 White Channel 11, N-43 Blue Channel 111, and N-44 Yellow Channel IV OUTPUT LIMITS Bistable NC305 SETPOINT AS-FOUND AS-LEFT As-Found Tolerance As-Left Tolerance Operability Limits

%  % Yo  % Yo  %

Overpower Low 20.0 ? 18.0 22.0 19.0 21.0 17.0 23.0 Setpoint Trip I I TECHNICAL SPECIFICATION LIMIT 5 27%

l(2) ICP 02.007 Series - Extended-Puwer Uprate Level New limits for N-41 Red Channel I, N-42 White Channel 11, N-43 Blue Channel 111, and N-44 Yellow Channel IV OUTPUT LIMITS Bistable NC305 SETPOINT AS-FOUND AS-LEFT As-Found Tolerance As-Left Tolerance Operability Limits

% Yo Yo  %  %  %

Overpower Low 20.0 ? 18.0 22.0 19.0 21.0 17.0 23.0 Setpoint Trip I I I TECI-INICAL SPECIFICATION LlMIT 5 27%

I OUTPUT LIMITS Bistable NC306 SETPOINT AS-FOUND AS-LEFT As-Found Tolerance ~ s - ~ eTolerance ft Operability Limits Overpower High 106.0 ? 104.0 108.0 105.0 107.0 103.0 108.0 Setpoint Trip TECHNICAL SPECIFICATION LIMIT 5 108%

WCfiENGINEERING CONSULTANTS Calculation No: 2009-0002 CALCULATION SHEETS Rev. No: 000-A Page: B2 of B2 Attachment B l(2) ICP 02.022 Series - Current Power Level New limits for N-41 Red Channel I, N-42 White Channel 11, N-43 Blue Channel 111, and N-44 Yellow Channel JSJ n:-A-~t-DJbldUlti OUTPUT LIMITS I NC305 AS-LEFT As-Found Tolerance As-Left Tolerance Operability Limits SETPOINT AS-FOUND Overpower Low Setpoint Trip 20.0% -? 18.0% 22.0% 19.0% 21.0% 17.0% 23.0%

I TECHNICAL SPECIFICATIONLIMIT 127%

l(2) ICP 02.022 Series - Extended Power Uprate Level New limits for N-41 Red Channel I, N-42 White Channel 11, N-43 Blue Channel 111, and N-44 Yellow Channel IV D:"',.Ll,. OUTPUT LMTS DtbLdUlG NC305 SETPOMT AS-FOUND AS-LEFT As-Found Tolerance As-Left Tolerance Operability Limits Overpower Low Setpoint Trip 20.0%  ? 18.0% 22.0% 19.0% 21.0% 17.0% 23.0%

I

• TECHNICAL SPECIFICATION L M T 5 27%

I OUTPUT LIMITS Bistable NC306 SETPOINT AS-FOUND LOW HIGH OUTPUT LIMITS Bistable NC306 SETPOINT AS-LEFT LOW HIGH

• Overpower High 85.0% -? 84.0% 86.0%

Setpoint Trip Reset 83.0% 4 82.0% 83.0%

TECHNICAL SPECIFICATIONLIMIT 5 108%

ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 261, EXTENDED POWER UPRATE TRANSMITTAL OF SAMPLE CALCULATIONS FOR REACTOR PROTECTION SYSTEM / ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SETPOINT CALCUATIONS ATTACHMENT 3 LOW RANGE CONTAINMENT PRESSURE UNCERTAINTYEETPOINTCALCULATION 16 pages follow

ENCINEERIING CONSULTANTS CALGULAT]hON TITLE PAGE Project 'Iient Or 441-005 Point Beach Nuclear Station Number: Station:

Total Calculation Revision PBNP-IC-17 003-A Number of 16 Number: Number:

Pages:

Title:

Low Range Containment Pressure Instrument UncertaintyISetpoint Original Calculation Revised Calculation [Zl Cancelled

[I7 Supersedes Calculation:

.' 1

w c l ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 2 of 15 REVISION

SUMMARY

SHEET Revision No. Description of the Revision 003-A This minor Revision incorporates double sided random uncertainties to calculate Limiting Trip Setpoints (LTSP) and revises the Field Trip Setpoint for the High Containment Pressure - SI Setpoint.

All the alpha-numeric changes made in this minor revision are marked with revision bars.

wcflENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev.No: 003-A Page: 3 of 15 CALCULATION TABLE OF CONTENTS SECTION PAGE CALCULATION TITLE PAGE ...........................................................................1 REVISION S-RY SHEET ..........................................................................2 CALCULATION TABLE OF CONTENTS ........................................................ 3 1.0 PURPOSE ....................................................................................................... 4 2.0 ACCEPTANCE CRITERIA ......................................................................... 4 3.0 ABBREVIATIONS ........................................................................................4

4.0 REFERENCES

...............................................................................................4 5.0 ASSUMPTIONS........................................... -..- ...................................... 4 6.0 DESIGN INPUTS ..........................................................................................4 7.0 METHODOLOGY ........................................................................................4 8.0 BODY OF CALCULATION ........................................................................ 5 9.0 RESULTS AND CONCLUSIONS .............................................................. 10 10.0 IMPACT ON PLANT DOCUMENTS........................................................ 14 11.0 ATTACHMENT LIST .................................................................................15 12.0 10 CFR 50.59172.48 REVIEW...................................................................... 15

a<&.!ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 4 of 15 1.0 PURPOSE The purpose of this minor revision is to calculate the Limiting Trip Setpoint (LTSP) for the Low Range Containment Pressure trips by applying double sided random uncertainties to the random portion of the Total Loop Error (TLE). This resolves the concern raised in CAP 01 173082.

2.0 ACCEPTANCE CRITERIA Same as Revision 3 of Calculation PBNP-IC-17.

3.0 ABBREVIATIONS Same as Revision 3 of Calculation PBNP-IC- 17.

4.0 REFERENCES

Same as Revision 3 of Calculation PBNP-IC-17.

5.0 ASSUMPTIONS Same as Revision 3 of Calculation PBNP-IC-17.

6.0 DESIGN INPUTS Same as Revision 3 of Calculation PBNP-IC-17.

7.0 METHODOLOGY 7.1 Uncertainty Determination Same as Revision 3 of Calculation PBNP-IC-17 except for section 7.1.6.

Limiting Trip Setpoint (LTSP) Equation summary The LTSP is determined by applying the Total Loop Error (TLE) to the AL or PL. The TLE consists of the combination of 95/95 double-sided random uncertainties and bias uncertainties. The uncertainty value associated with the double-sided distributions is larger than the value associated with the single-sided distributions. Therefore, including double-sided random uncertainties in the TLE is an acceptable, conservative deviation from the guidance in DG-I01 (Reference G. I), which permits smaller single-sided random uncertainties.

In 2010, NRC advised Point Beach that the NRC would no longer accept the use of single-sided random uncertainties for determining Limiting Safety System Settings (LSSS) in the plant Technical Specifications. Double-sided uncertainties in the random portion of the TLE term yields a more conservative LTSP value than an LTSP based on single-sided uncertainties. Therefore, a TLE based on double-sided uncertainties is appropriate and acceptable for LSSS values.

%cfJ ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SI-IEETS Rev. No: 003-A Page: 5 of 15 For a process increasing toward the analytical limit, the calculated Limiting Trip Setpoint is as follows:

For a process decreasing from normal operation toward the analytical limit, the calculated Limiting Trip Setpoint is deterrnined as follows:

7.2 Drift Consideration Same as Revision 3 of Calculation PBNP-IC- 17.

8.0 BODY OF CALCULATION Determination of Process Error Same as Revision 3 of Calculation-PBNP-IC-17.

Device Uncertainty Analysis Same as Revision 3 of Calculation PBNP-IC-17.

Device Uncertainty Summary Same as Revision 3 of Calculation PBNP-IC-17.

Total Loop Errors Same as Revision 3 of Calculation PBNP-IC-17.

Acceptable As -Left and As-Found Tolerances Same as Revision 3 of Calculation PBNP-IC-17.

Setpoint Evaluations High Containment Pressure - Safety Injection and Condensate Isolation Actuation Setpoint Evaluation For an increasing setpoint towards Analytical Limit, Equation 7.1.6-1 is used.

LTSP = AL - TLETRIp Where:

AL = 6 psig Section 6.5 TLETw = + 0.808 psi Section 8.4.1

=$:I ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 6 of 15 Substituting, I LTSP = 6 - 0.808 psj II LTSP = 5.192 psig (95195)

From Section 6.5, the existing Field Trip Setpoint (FTSP) for High Containment Pressure - Safety Injection and High Containment Pressure - Condensate Isolation is 5 psig. While the existing FTSP is conservative compared to the calculated LTSP, it is non-conservative considering the Operability Limits (i.e., 5.24 psig from base calculation) based on the existing FTSP of 5 psig. Therefore, to prevent an overlap between the new LTSP and the OL values, a new FTSP of 4.8 psig is recommended in accordance with Section 2.0 for High Containment Pressure - Safety Injection and Condensate Isolation trip.

I The margin between LTSP and the recommended FTSP is calculated as follows.

Margin = LTSP - FTSP Where:

LTSP = 5.192 psig FTSP = 4.8 psig Substituting, I Margin = 5.192 psig - 4.8 psig I Margin = 0.392 psi 8.6.2 High-High Containment Pressure - Containment Spray Trip Setpoint Evaluation For an increasing setpoint towards Analytical Limit, Equation 7.1.6-1 is used.

I LTSP = AL -TLETm Where:

t AL = 30 psig Section 6.5 TLETRp = rt 0.808 psi Section 8.4.1 Substituting, LTSP = 30 - 0.808 psi LTSP = 29.192 psig (95195)

From Section 6.5, the Field Trip Setpoint (FTSP) for High-High Containment Pressure

- Containment Spray Actuation setpoint is 25 psig. The FTSP is conservative compared to the calculated LTSP. Per Section 2.0, this setpoint is acceptable, and may be retained.

GcClENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 7 of 15 The margin between LTSP and FTSP is calculated as follows.

Margin = LTSP - FTSP Where:

I LTSP = 29.192 psig FTSP = 25.0 psig Section 6.5 Substituting, Margin = 29.192 psig - 25.0 psig Margin = 4.192 psi 8.7 Operability Limit (OL) Evaluation Same as Revision 3 of Calculation PBNP-IC-17 except section 8.7.1.

8.7.1 High containment Pressure - Safety Injection and Condensate Isolation Actuation Operability Limit Evaluation Using Equation 7.1.7-3 to determine the bistable 30 drift value, Rd3, = (1.5) Rd2, (Eq. 7.1.7-3)

Rd3, = (1.5) 0.212 % span (Rd2, from Section 8.2.13)

Rd3, = k 0.3 18 % span For the transmitter range of -6 psig to 54 psig, the recommended FTSP for the high containment pressure-safety injection and condensate isolation actuation of 4.8 psig, expressed as percent span is:

I FTSP = ([4.8 - (-6)] + 60)

• 100 = 18.0 % span Using Equation 7.1.7-1, the OL' is determined as:

OL' = FTSP + [BAL~+ ~ d 3 2 ] " (Eq. 7.1.7-1)

OL+= 18.0 % + (0.250~+ 0.318~)" (BAL from Section 8.5.1.2)

OL+= 18.0 % + 0.405 OL+= 18.405% span I Expressed in psig, OL' = (0.18405

• 60) + (-6) = 5.04 psig

a $ : g ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 8 of 15 Using Equation 7.1.7-2 the OL- is determined as:

OL- = FTSP - [BAL~+ ~d3:]" (Eq. 7.1.7-2)

OL- = 18.0 % - (0.250~+ 0.318~)" (BAL from Section 8.5.1.2)

OL- = 18.0 % - 0.405 OL- = 17.595 %span I Expressed in psig, OL- = (0.17928

• 60) + (-6) = 4.56 psig Because the High Containment Pressure - Safety hjection and Condensate Isolation I actuation is an increasing trip, the positive OL' value of 5.04 psig should be the limit compared to the COT as-found value to determine Technical Specification operability of the channel. However, an as-found value found outside either the OL' or OL-indicates that the channel is operating abnormally.

8.8 Channel Check Tolerances Same as Revision 3 05Calculation PBNP-IC-17.

8.9 Scaling Same as Revision 3 of Calculation PBNP-IC-17 except section 8.9.1.

8.9.1 High Containment Pressure - Safety Injection and Condensate Isolation FTSP and Operability Limits From Table 6.3- 1, the model number of the transmitters is Foxboro N-E 11GM-HIB I -

BELIAEL. From Reference V.2, the transmiaers have a 10 to 50 mAdc output range corresponding to an input of -6 to 54 psig (Ref. P.3 and P.4).

m =( ~ -2 y1) 1(x2 - x1) Equation 7.1.8-2 Where:

xl = -6 psig x2 = 54 psig yl = 10 mAdc y2 = 50 mAdc Substituting, m = [(50 mAdc) - (10 mAdc)] / [(54 psig) - (-6 psig)]

m = 40 mAdc1 60 psi

ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 9 of 15 Solving for the equivalent signal in mAdc corresponding to the FTSP of 4.8 psig y =m*(x-xl)+yl Equation 7.1.8-3 Where:

x = 4.8 psig Section 8.6.1 XI = -6 psig y =FTSP (mAdc) yl = 10 mAdc Substituting, y = [(40 mAdcl60 psi) * (4.8 psig - (-6 psig))] + 10 mAdc y = 17.20 mAdc Converting to Vdc-due to a 10 SZ resistor across the calibration point (Ref.

D.12 through D.17) y ' = 17.3 mAdc

• 1 0 R I 1OOOmVdcperVdc y =0.172Vdc For an OL' of 5.04 psig (Section 8.7.1) the equivalent equation is:

y =m*(x-xl)+yl Equation 7.1.8-3 Where:

I x = 5.04 psig XI = -6 psig y = OL' (mAdc) yl = lOmAdc Substituting, y = [(40 mAdcl60 psi) * (5.04 psig - (-6 psig))] + 10 mAdc y = 17.36 mAdc Converting to Vdc due to a 10 R resistor across the calibration point (Ref. D.12 through D.17) y =17.36rnAdc* 10R11000mVdcperVdc y ~ 0 . 1 7 3 6Vdc

a c g ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 10 of 15 I For an OL-of 4.56 psig (Section 8.7.1) the equivalent equation is:

y =m*(x-xl)+yl Equation 7.1.8-3 where:

I x = 4.56 psig XI = -6 psig

-y = OL- (mAdc) yl = 10 rnAdc Substituting, y = [(40 d d c / 60 psi) * (4.56 psig - (-6 psig))] + 10 mAdc y = 17.04 mAdc Converting to-Vdc due to a 10 R resistor across the calibration point (Ref. D. 12 through D.17) y = 17.0-4rnAdc* 1 0 R / 1000mVdcperVdc y = 0.1704 Vdc Table 8.9-1 I l(2)PC-945A/B, 947A/B, 949A/B - High Containment Pressure Bistable Calibration - Safety Injection and Condensate Isolation Function Input (psig) Output (rnAdc) Output (Vdc)

OL+ 5.04 17.36 0.1736 FTSP? 4.8 17.20 0.1720 OL- 4.56 17.04 0.1704 9.0 RESULTS AND CONCLUSIONS, WITH LIMITATIONS 9.1 Analytical Limits (AL)

Same as Revision 3 of Calculation PBNP-IC-17.

@cg ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 11 of 15 Operability Limits (OL)

Same as Revision 3 of Calculation PBNP-IC-17, except for the following changes:

For recommended Technical Specification values for High Containment Pressure -

Safety InjectionICondensate Isolation and Containment Spray, see Section 9.3.

Table 9.2-1 Operability Limits Function . . Calculated OL' and OL- Reference High containment pressure - Safety OL' 5.04 psig Injection and Condensate Isolation Section 8.7.1 Actuation OL- 4.56 psig High-High Containment Pressure - OL' 25.24 psig Section 8.7.2 Containment Spray OL- 24.76 psin

-LimitingTrip Setpoin$s@TSP) and Field Trip Setpoints (FTSP)

This calculation has determined a new Field Trip Setpoint (FTSP) for High Containment Pressure - Safety Injection and Condensate Isolation trip. PBNP should evaluate the proposed FTSP of 4.8 psig for adequacy.

This calculation has detennined that the Field Trip Setpoint (FTSP) for High-High Containment Pressure - Contaimnent Spray trip is conservative with respect to the calculated LTSP and may be retained.

Table 9.3-1 Limiting Trip SetpointsIField Trip Setpoints Calculated ESFAS Function FTSP Margin Reference LTSP I High Contaimnent I I I I Pressure - Safety Injection and 1 5.192 psig / 4.8 psig 1 0.392 psi I Section 8.6.1 Condensate Isolation High-High Containment Pressure - 29.192 psig (+) 25 psig 4.192 psi Section 8.6.2 I Containment Spray I Note Jf: Based on the calculated LTSPs, it is recommended that the Technical Specification 3.3.2 Allowable Values for High Containment Pressure - Safety Injection I Condensate Isolation and Contaimnent Spray be rounded down from the LTSPs shown here.

Tech Surveillance Same as Revision 3 of Calculation PBNP-IC- 17.

w C 1ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION S E E T S Rev. No: 003-A I Page: 1 12 of 15 I 9.5 EOP Inputs Same as Revision 3 of Calculation PBNP-IC- 17.

9.6 Channel Check Tolerances Same as Revision 3 of Calculation PBNP-IC- 17.

9.7 Acceptable As-Left And As Found Tolerances Same as Revision 3 of Calculation PBNP-IC-17.

9.8 Scaling Table 9.8-1 Scaling Values Input Output Output Setpoints Function Reference (psig) (mAdc) (Vdc)

OL+ 5.04 17.36 0.1736 8.9.1 High As-Found 5.00 17.33 0.1733 8.5.2.2 Containment As-Left 4.95 17.30 0.1730 8.5.1.2 Pressure - Safety 8.6.1 FTSP? 4.8 17.20 0.1720 Injection and As-Left 4.65 17.10 0.1710 8.5.1.2 Condensate AS-Found 4.60 17.07 0.1707 8.5.2.2 Isolation OL' 4.56 17.04 0.1704 8.9.1 OL+ 25.24 30.83 0.3083 8.9.1 High-High As-Found 25.20 30.80 0.3080 8.5.2.2 Containment As-Left 25.15 30.77 0.3077 8.5.1.2 Pressure - FTSP? 25 30.67 0.3067 6.5 Containment As-Left 24.85 30.57 0.3057 8.5.1.2 Spray As-Found 24.80 30.54 0.3054 8.5.2.2 OL- 24.76 30.51 0.3051 8.9.1 9.9 Limitations Same as Revision 3 of Calculation PBNP-IC- 17.

acIlENGINEERING CONSULTANTS Calculation No: PBNP-LC-17 CALCULATION SHEETS Rev. No: 003-A Page: 13 of 15 9.10 Graphical Representation of the Setpoints 9.10.1 High Containment Pressure - Safety Injection and Condensate Isolation Setpoints Figure 9.10-1 High Containment Pressure - Safety Injection and Condensate Isolation Bistable (PC-945A, 947A, 949A)

Analytical Limit ( A , ) 6.0 psig Limiting Trip Setpoint (LTSP) 5.192 psig 5.04 psig (0.1736 Vdc) 5.0 psig (0.1733 Vdc) 4.95 psig (0.1730 Vdc) 1 Field Trip Setpoint (FTSP) 4.8 psig (0.1720 Vdc)

-As-Left 4.65 psig (0.1710 Vdc)

-As-Found 4.60 psig (0.1707 Vdc)

-Operability Liinit (OL-) 4.56 psig (0.1704 Vdc)

I 9.10.2 High-High Containment Pressure - Containment Spray Setpoint Figure 9.10-2 High-High Containment Pressure - Containment Spray Bistable (PC-945B, 947B, 949B)

Analytical Limit (AL) 30.0 psig Limiting Trip Setpoint (LTSP) 29.192 psig

+Operability Limit ( O L ~ 25.24 psig (0.3083 Vdc)

+As-Found 25.20 psig (0.3080 Vdc)

+As-Left 25.15 psig (0.3077 Vdc)

Field Trip Setpoint (FTSP) 25.0 psig (0.3067 Vdc)

-As-Left 24.85 psig (0.3057 Vdc)

-As-Found 24.80 psig (0.3054 Vdc)

-Operability Limit (OL-) 24.76 psig (0.305 1 Vdc)

a c f iENGTNEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 14 of 15 10.0 IMPACT ON PLANT DOCUMlENTS As a result of this minor revision, following documents need to be revised.

lICP 02.001RD7"Reactor Protection and Engineered Safety Features Red Channel Analog 92 Day Surveillance Test7'. See Attachment A for changes.

2ICP 02.001RD7"Reactor Protection and Engineered Safety Features Red Channel Analog 92 Day Surveillance Test". See Attachment A for changes.

1ICP-02.001BL7"Reactor Protection and Engineered Safety Features Blue Channel Analog 92 Day Surveillance Test". See Attachment A for changes.

2ICP-02.001BL, "Reactor Protection and Engineered Safety Features Blue Channel Analog 92 Day Surveillance Test7'. See Attachment A for changes.

1ICP-02.001WH7"Reactor Protection and Engineered Safety Features White Channel Analog 92 Day Surveillance Test". See Attachment A for changes.

2ICP-02.001WH7"Reactor Protection and Engineered Safety Features White Channel Analog 92 Day Surveillance Test7'. See Attachment A for changes.

lICP 02.020RD7"Post-Refueling Pre-Startup-RPS and ESF Red'Channel Analog Surveillance Test7'. See Attachment A for changes.

21CP 02.020RD, "Post-Reheling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test". See Attachment A for changes.

1ICP 02.020BL7"Post-Refueling Pre-Startup RPS and ESF Blue Channel Analog Surveillance Test7'. See Attachment A for changes.

21CP 02.020BL7"Post-Refueling Pre-Startup RPS and ESF Blue Channel Analog Surveillance Test7'. See Attachment A for changes.

IICP 02.020WH7"Post-Refueling Pre-Startup RPS and ESF White Channel Analog Surveillance Test". See Attachment A for changes.

2ICP 02.020WH7"Post-Refueling Pre-Startup RPS and ESF White Channel Analog Surveillance Test". See Attachment A for changes.

STPT 2.1, "Setpoint Document - Safety Injection7'. New Tech Spec Allowable Value needs to be incorporated.

STPT 2.3, "Setpoint Document - Containment Pressure and LTOP". New Tech Spec Allowable Value needs to be incorporated.

DBD-30, "Containment Heating and Ventilation Systems7'. Revise section 2.2.3, page 2-16 to change the Containment High Pressure Setpoint from 5.0 psig to 4.8 psig.

Technical Specifications 3.3.2 (ESFAS) to be revised after NRC approval of EPU License Amendment Request. Allowable Values for high and high-high containment pressure will be revised to rounded down values of the LTSP shown on Figures 9.10-1 and 9.10-2. The TRM may also be revised to include the operability limits shown on these diagrams.

a c t ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: 15 of 15 11.0 ATTACHMENT LIST Same as Revision 3 of Calculation PBNP-IC-17, except Attachment A.

12.0 10 CFR 50.59172.48 REVIEW The 10 CFR 50.59172.48 review performed as part of base calculation is applicable to this minor revision. Hence, no separate 10 CFR 50.59172.48 review is required.

a C 8 ENGINEERING CONSULTANTS Calculation No: PBNP-IC-17 CALCULATION SHEETS Rev. No: 003-A Page: A1 of A1 ATTACHMENT A Same as Revision 3 of Calculation PBNP-IC-17, except the following changes:

l(2)ICP 02.01RD. BL, WH and l(2)ICP 02.020RD, BL, WH 1 ( 2 ) ~ ~ - 9 4 5 ~947A/B,

&, 949A/B Coptainment Pressure Output (Containment As-Found Limits Operability Limits As-Left Limits Process Pressure)

Containment Setpoint As- As-Pressure Setpoint ~ o u n d Left Low High Low High Low High I psig Vdc Vdc Vdc Vdc Vdc Vdc Vdc Vdc Vdc Safety I h j ection 4.8 0.17201' 0.1710 0.1730 0.1707 0.1733 0.1704 0.1736 Containment 0.3054 0.3080 0.3051 25.0 0.30671' 0.3057 0.3077 0.3083 Spray Logic 5 Technical Specification Limit l(2)-PC-945A, 947A, 949A (To be specified by PBNP later)

(Ref: Calculation PBNP-IC- 17) s Technical Specification Limit 5 1(2)-PC-945B, 947B, 949B (To be specified by PBNP later)

- (Ref: Calculation PBNP-IC- 17)

ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 261, EXTENDED POWER UPRATE TRANSMllTAL OF SAMPLE CALCULATIONS FOR REACTOR PROTECTION SYSTEM / ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SETPOINT CALCUATIONS STEAM LINE PRESSURE INSTRUMENT LOOP UNCERTAINTY/SETPOINT CALCULATION 19 pages follow

r ENGINEERING CONSULTANTS CfiC'BtTLATIONTITLE PAGE Project Client or Number:

441-005 Station:

Point Beach Nuclear Station Calculation Revision Total Number PBNP-IC-3 9 Number:

004-A of Pages:

19 Number:

Title:

Steam Line Pressure Instrument Loop Uncertainty / Setpoint Calculation Original Calculation Revised Calculation Cancelled EI] Supersedes Calculation:

Nuclear Safety Related:

HUES O N ~ QA Scope: BYES UNQ System: W Date of Issue: See Approval Date SIGNAT S AND DATES Preparer Reviewer Discipline Name Signature Date El I&C Saravanan Makayee b,. - / b I@ )I..

El

• I&C Anup Behera & 6izb/io q q 171 El q Approver: Name: Badar Hussain Signature: 8..k

-i---

Date:

%Ci ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 2 of 18 REVISION

SUMMARY

SHEET Revision No. Description of the Revision 004-A This minor revision incorporates double-sided random uncertainties to calculate Limiting Trip Setpoint (LTSP) and revises the Field Trip Setpoint for the Low Steam Line Pressure Safety Injection trip for the EPU condition.

All the alpha-numeric changes made in this minor revision are marked up revision bars.

aC!4 ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev.No: 004-A Page: 3 of 18 CALCULATION TABLE OF CONTENTS SECTION PAGE CALCULATION TITLE PAGE ...............................................................................1 REVISION

SUMMARY

SHEET............................................................................-2 CALCULATION TABLE OF CONTENTS ............................................................3 1.0 PURPOSE .........................................................................................................

4 2.0 ACCEPTANCE CRITERIA ...........................................................................-4 3.0 ABBREVIATIONS ......................................................................................... 4

4.0 REFERENCES

................................................................................................4 5.0 ASSUMPTIONS .............................................................................................-4 6.0 DESIGN INPUTS ............................................................................................4 7.0 METHODOLOGY .........................................................................................-4 8.0 BODY OF CALCULATION..........................................................................-5 9.0 RESULTS AND CONCLUSIONS.................................................................11 10.0 IMPACT ON PLANT DOCUMENTS ...........................................................17 11.0 ATTACHMENT LIST...................................................................................-18 12.0 10CFR50.59 REVIEW ...................................................................................18

WCR ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 4 of 18 PURPOSE The purpose of this minor revision is to calculate the Limiting Trip Setpoint (LTSP) for Low Steam Line Pressure Safety Injection trip by applying double-sided random uncertainties to the random portion of the Total Loop Error (TLE).

This resolves the concern raised in CAP 01 173082.

ACCEPTANCE CRITERIA Same as Revision 4 of calculation PBNP-IC-39.

ABBREVIATIONS Same as Revision 4 of calculation PBNP-IC-39.

REFERENCES Same as Revision 4 of calculation PBNP-IC-39.

ASSUMPTIONS Same as Revision 4 of calculation PBNP-IC-39.

DESIGN INPUTS Same as Revision 4 of calculation PBNP-IC-39.

METHODOLOGY Uncertainty Determination Same as Revision 4 of calculation PBNP-IC-39.

Drift Considerations Same as Revision 4 of calculation PBNP-IC-39.

Channel Check Tolerance Equation Summary (CCT)

Same as Revision 4 of calculation PBNP-IC-39.

Setpoint Calculations For setpoints that are based on an Analytical Limit (AL) or Process Limit (PL), a Limiting Trip Setpoint (LTSP) shall be calculated. The LTSP represents the most limiting value a channel trip setpoint can have that will ensure the AL or PL is not exceeded, considering all credible instrument channel errors that can exist between successive calibrations. The LTSP provides the basis for establishing an Allowable Value (AV) in the Technical Specifications.

The LTSP is determined by applying the Total Loop Error (TLE) to the AL or PL.

The TLE consists of the combination of 95/95 double-sided random uncertainties and bias uncertainties. The uncertainty value associated with the double-sided

a 4 f : I ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 5 of 18 distributions is larger than the value associated with the single-sided distributions.

Therefore, including double-sided random uncertainties in the TLE is an acceptable, conservative deviation from the guidance in DG-I01 (Reference G. I),

which permits smaller single-sided random uncertainties. In 2010, NRC advised Point Beach that the NRC would no longer accept the use of single-sided random uncertainties for determining Limiting Safety System Settings (LSSS) in the plant Technical Specifications. Double-sided uncertainties in the random portion of the TLE term yields a more conservative LTSP value than an LTSP based on single-sided uncertainties. Therefore, a TLE based on double-sided uncertainties is appropriate and acceptable for LSSS values.

Consistent with the methodology of Reference G. 1, random and bias portions of the TLE are calculated separately and are then combined using an appropriate sign convention based on the direction that the process variable approaches the setpoint.

For a process increasing toward the Analytical Limit, the calcul~tedLimiting Trip Setpoint is as follows:

For a process decreasing toward the Analytical Limit, the calculated Limiting Trip Setpoint is as follows:

7.5 Process Error Calculation Same as Revision 4 of calculation PBNP-IC-39.

8.0 BODY OF CALCULATION 8.1 Device Uncertainty Analysis Same as Revision 4 of calculation PBNP-IC-39.

8.2 Device Uncertainty Summary Same as Revision 4 of calculation PBNP-IC-39.

8.3 Total Loop Error Same as Revision 4 of calculation PBNP-IC-39.

8.4 Acceptable As-Found and As-Left Calibration Tolerance Same as Revision 4 of calculation PBNP-IC-39.

GCCH ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 6 of 18 8.5 Channel Check Tolerance Same as Revision 4 of calculation PBNP-IC-39.

Low Steam Line Pressure Safety Injection Setpoint According to Section 7.4, for decreasing setpoints:

LTSP&=AL + [TLElaqdmf + TLE~~-~~~~+]:I'PS Where:

AL = 320.3 psig (Existing); 395.3 psig (EPU) (Section 6.7)

TLEla,dm+ = + 8.097 % span (Section 8.3.1)

TLEl,bi,+ = + 1.808% span (Section 8.3.1)

PS = 1400 psi Combine TLE to be used in the LTSP equation:

TLEI, = 9.905% span Converting to process units, TLEla = 138.67 psi Existing LTSP:

Substituting TLEla value in the LTSP equation:

LTSP = 320.3 psig + 138.67 psi LTSP = 458.97 psig (Existing)

From Section 6.7, the actual Field Trip Setpoint (FTSP) for Low Steam Line Pressure Safety Injection is 530 psig. The FTSP is conservative for a decreasing setpoint compared to the calculated LTSP. Per Section 2.0, this setpoint is acceptable, and may be retained. In addition, per Section 6.7.4, the FTSP of 530 psig is not lower than the backup trip process limit of 500 psig and, therefore, may be retained.

a C i ENGINEERING CONSULTANTS Calculation No: PBNP-BC-39 CALCULATION SHEETS Rev. No: 004-A Page: 7 of 18 EPU LTSP:

Substituting TLEI, value in the LTSP equation:

LTSP = 395.3 psig + 138.67 psi LTSP = 533.97 psig (EPU)

From Section 6.7, the existing Field Trip Setpoint (FTSP) for Low Steam Line Pressure Safety Injection is 530 psig. The FTSP is non-conservative for a decreasing setpoint compared to the calculated LTSP for EPU condition and hence, not acceptable. In accordance with the criteria outlined in Sections 2.0 and 6.7.4, a new Field Trip Setpoint of 545 psig is recommended for Low Steam Line Pressure Safety Injection trip. The recommended FTSP value of 545 psig for the EPU condition will provide sufficient margin such that the lower as-found value for the new E S P will not overlap the recommended Allowable Value of 535 psig, which is the EPU LTSP conservatively rounded up (see Section 8.7).

Margin Between LTSP and FTSP:

The margin between LTSP and ITSP is calculated as follows:

Margin= FTSP - LTSP Where:

LTSP = 458.97 psig (Existing); 533.97 psig (EPU)

FTSP (Existing) = 530 psig (Section 6.7)

FTSP (EPU) = 545 psig (Proposed)

Substituting this value, Margin (Existing) = 530 psig - 458.97 psig Margin (EPU) = 545 psig - 533.97 psig Margin = 71.03 psi (Existing); 11.03 psi (EPU)

a 6 f ENGINEERING f CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 8 of 18 8.7 Allowable Value (AV) Evaluation From Section 8.6, the Limiting Trip Setpoint (LTSP) is as follows:

LTSP = 458.97 psig (Existing)

LTSP = 533.97 psig (EPU)

Existing Condition: -

From Section 6.7, the existing Tech Spec Allowable Value (AV) for Low Steam Line Pressure is 2 500 psig. The existing Tech Spec Allowable Value of 500 psig ,

is conservative for a decreasing setpoint compared to the calculated LTSP (Existing) of 458.97 psig and hence, acceptable.

EPU Condition:

For EPU condition, based on the calculated value of LTSP (i.e., 533.97 psig), the EPU Tech Spec Allowable Value (AV) of 2 535 psig is recommended for Low Steam Line Pressure.

8.7.1 Low Steam Line Pressure Safety Injection Trip Operability Limit Using Equation 7.1.6-3 to determine the bistable 30 drift value, Rd3, = (1.5) 0.212 % span (Rd', from Section 8.1.3 1)

Rd3, = + 0.3 18 % span Existing Condition:

The FTSP for the Low Steam Line Pressure Safety Injection Trip of 530 psig (Section 6.7), expressed as percent span, is:

FTSP = ([530 - 01 + 1400) 4: 100 = 37.86 % span Using Equation 7.1.6- 1, the OLf is determined as:

OLf = FTSP + [RAL' + ~d33" (Eq. 7.1.6-1)

OL' = 37.86 % i- (0.500' + 0.318'fh (RAL is Bv from Section 8.1.33)

OLf = 37.86 % + 0.593 OLf = 38.45 % span

ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 9 of 18 Expressed in psig, OLf = (0.3845

• 1400) + 0 = 538.3 psig; Rounded down to 538 psig for calibration.

Using Equation 7.1.6-2, the OL- is determined as:

OL- = FTSP - [RAL2 + ~d3,2]" (Eq. 7.1.6-2)

OLf = 37.86 % - (0.500~+ 0.318~)" (RAL is Bv from Section 8.1.33)

I OL- = 37.86 % - 0.593 OL- = 37.27 % span Expressed in psig, OL- = (0.3727 :I: 1400) + 0 = 521.8 psig; Rounded up to 522 psig for calibration.

Because the Low Steam Line Pressure Safety Injection Trip is a decreasing trip, the negative OL- value of 522 psig should be the limit compared to the COT as-found value to determine Technical Specification operability of the channel for the existing plant condition. However, an as-found value found outside either the OLf or OL- indicates that the channel is operating abnormally.

I EPU Condition:

The proposed FTSP (EPU) for the Low Steam Line Pressure Safety Injection Trip of 545 psig (Section 8.6), expressed as percent span, is:

FI'SP = ([545 - 0] s 1400)

• 100 = 38.93 % span Using Equation 7.1.6- 1, the OLf is determined as:

OL' = FTSP + [RAL2 + ~d3,2]" (Eq. 7.1.6-1)

OL' = 38.93 % + (0.500~+ 0.318~)" (RAL is Bvfrom Section 8.1.33)

OLf = 38.93 % + 0.593 OL' = 39.52 % span Expressed in psig, OLf = (0.3952

• 1400) + 0 = 553.28 psig; Rounded down to 553 psig for calibration.

a c fENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 10 of 18 I Using Equation 7.1.6-2, the OL- is determined as:

OL- = R S P - [RAL~ + ~d3,2]" (Eq. 7.1.6-2)

OL- = 38.93 % - (0.500' + 0.318')" (RAL is Bv from Section 8.1.33)

OL- = 38.93 % - 0.593 OL- = 38.34 % span Expressed in psig, OL- = (0.3834

• 1400) + 0 = 536.76 psig; Rounded up to 537 psig for calibration.

Because the Low Steam Line Pressure Safety Injection Trip is a decreasing trip, the negative OL- value of 537 psig should be the limit compared to the COT as-found value to deterrnine Technical Specification operability of the channel during the EPU condition. However, an as-found value found outside either the OLf or OL- indicates that the channel is operating abnormally.

8.7.2 Scaling (Existing & EPU) for Low Steam Line Pressure Safety Injection Trip FTSP and Operability Limits I The output signal corresponding to the process value variable is deterrnined using Equation 7.1.7-3, y = m$:(x-xl)+yl Where:

x = Process value (psig) xl = 0 psig y = Output signal (Vdc) yl = 0.1 Vdc m =(~z-~l)+(xl-xl)

Where:

y2 = 0.5 Vdc yl ~ 0 . Vdc 1

x2 = 1400 psig xl = 0 psig Using the above equation, the output signal for various process value related to Low Steam Line Pressure Safety Injection Trip is summarized below:

acIfENGSNEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 11 of 18 Table 8.7-1: l(2) PC-468,469,478,479,482,483 BistabIe Calibration Existing Condition EPU Condition Output Process Parameter Process Output Section Section (Vdc) (Psig) (Psig) (Vdc) 8.7.1 0.2537 538 OL+ 553 0.2580 8.7.1 8.4.2.6 0.2536 7 537.6 AF+ 552.6 0.2579 7 8.4.2.6 8.4.1.6 0.2534 537 AL+ 552 0.2577 8.4.1.6 6.7 0.2514 530 FrSP 545 0.2557 8.6 8.4.1.6 0.2494 523 AL- 538 0.2537 8.4.1.6 8.4.2.6 0.2492 522.4 AF- 537.4 0.2535 8.4.2.6 8.7.1 0.2491 522 OL- 537 0.2534 8.7.1 8.7 0.2429 500 AV 535 0.2529 8.7 Note ?:A sample output signal calculation corresponding to the existing and the EPU As-Found+ is shown below:

1) For the existing As-Found+ value of 537.6 psig (530 psig + 7.6 psi from Section 8.4.2.6), the output signal is calculated as follows:

y = [(0.4 Vdcl 1400 psig) :k (537.6 psig - 0 psig)] + 0.1 Vdc y ~ 0 . 2 5 3 6Vdc

2) For the EPU As-Found+ value of 552.6 psig (545 psig + 7.6 psi from Section 8.4.2.6), the output signal is calculated as follows:

y = r(0.4 Vdc/ 1400 psig) * (552.6 psig - 0 psig)] + 0.1 Vdc y = 0.2579 Vdc 8.8 Parametric Value Evaluation Same as Revision 4 of calculation PBNP-IC-39.

9.0 RESULTS AND CONCLUSIONS 9.1 Total Loop Error Same as Revision 4 of calculation PBNP-IC-39, except for Total Bistable Loop Error (TLE1,).

ACCIDENT Ref.

95/95 Section Span psi Total Bistable Loop Error (TLEI,) +9.905% +138.67 8.6

W C l ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 12 of 18 9.2 Acceptable As-Left and As-Found Tolerances Same as Revision 4 of calculation PBNP-IC-39.

9.3 Limiting Trip Setpoints, Operability Limits (OL), and Recommended Tech Spec Changes AR 89661 1 determined that the Technical Specification Allowable Values for several protection system functions in TS 3.3.1 (RPS) and TS 3.3.2 (ESFAS) were non-conservative. As a result, the I&C calibration procedures were revised to install temporary administrative limits (termed Allowable Limits in the ICPs) on the trip bistable as-found values until a license amendment is approved to revise the TS sections.

The Limiting Trip Setpoints for primary trip functions determined in this calculation provide new Technical Specification limits (Allowable Values) for channel operability to protect the accident analyses Analytical Limits. The LTSPs also satisfy the definition of a Limiting Safety System Setting in 10CFR50.36.

Backup trips and permissives do not have a LTSP that can be used as an Allowable Value in Tech Specs because there is no analytical limit to "anchor" I the LTSP. Therefore, it is recommended that a conservatively rounded version of the LTSPs for the primary trip functions be included in a license amendment to revise RPS TS 3.3.1, Table 3.3.1-1 and ESFAS TS 3.3.2, Table 3.3.2-1 Allowable Values.

Operability Limits have been determined for all trip functions (primary trips, backup trips, and the SI BlocMUnblock function). The OLs provide new limits to be applied in the I&C calibration procedures for establishing Technical Specification operability of the trip channels during Channel Operational Testing (COT).

It is recomended that the Operability Limits for both primary and backup trips be included in the Technical Requirements Manual (TRM) as limits (more restrictive than the LTSPs) for establishing channel operability during channel surveillance testing. The reason for including OLs in the TRM rather than the Technical Specifications is to allow the station flexibility to revise the field setpoint values, along with their as-left, as-found, and OL values, without requiring prior NRC approval. The LTSPs, which provide protection for the accident analyses, are the appropriate Allowable Values for the protection functions in the Specifications and would remain bounding limits for the primary trips (only).

For the results of Limiting Trip Setpoint (LTSP) and Tech Spec Allowable Value (AV), see Sections 9.5 and 9.6, respectively.

wC81ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 13of 18 I The following Operability Limits are proposed to be added to the bistable calibration procedures, as shown in the procedure markups in Attachment A.

Table 9.2-1: Operability Limits for Existing and EPU Conditions Existing EPU Function Reference Reference Condition Condition Low Steam Line OL+538 psig Section 8.7.1 OLf 553 psig OL. 537 Section 8.7.1 Pressure Safety OL. 522 psig Injection Trip 9.4 Channel Check Tolerance Same as Revision 4 of calculation PBNP-IC-39.

9.5 Setpoint Evaluations The following LTSPs and FTSPs with associated Margins have been determined for Existing and EPU operations.

Table 9.4-la: Setpoints (Existing)

Existing Existing Field Existing Limiting Trip Trip Setpoint Reference Margin Setpoints 458.97 psig 530 psig 7 1.03 psi Section 8.6 Table 9.4-lb: Setpoints (EPU)

EPU Limiting Proposed EPU Field EPU Reference Trip Setpoints Trip Setpoint Margin I 533.97 psig 545 psig (Note T) 11.03 psi Section 8.6 Note This calculation has determined that the existing FTSP value of 530 psig for Low Steam Line Pressure Safety Injection is non-conservative compared to the calculated LTSP value of 533.97 psig for the EPU condition. Therefore, it is recommended that the FTSP value for Low Steam Line Pressure Safety Injection @PU condition) be revised to 545 psig, such that the lower Operability Limit of the new FTSP will be greater than the proposed new Allowable Value of 2 535 psig (which is based on rounding up the calculated LTSP of 533.97 psig)..

E N G M E R I N G CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 14 of 18 1 9.6 Technical Specification Allowable Values I The following Technical Specification Allowable Values (AV) have been determined for Existing and EPU operations.

Table 9.5-la: Allowable Values (Existing)

Reference Value Table 9.5-lb: Allowable Values (EPU)

I Proposed EPU Allowable Value I Reference I I

I I 2535 psig (Note t) I Section 8.7 I Note-?: This calculation has determined that the existing Tech Spec Allowable Value of 500 psig for Low Steam Line Pressure safety Injection is non-conservative compared to the calculated LTSP value of 533.97 psig for the EPU condition. .

Based on the calculated LTSP for the EPU condition, it is recommended that the Technical Specification Table 3.3.2-1 Allowable Value for Low Steam Line Pressure Safety Injection be revised to 2 535 psig, which is the LTSP value conservatively rounded up.

1 9.7 Parametric Value Evaluation Same as Revision 4 of calculation PBNP-IC-39.

( 9.8 Limitations Same as Revision 4 of calculation PBNP-IC-39.

1 -1 ENGINEERING CONSULTANTS 1 I Calculation No: PBNP-IC-39 I I CALCULATION SHEETS I Rev. No: I 004-A I I Page: 1 15 of 18 I 1 9.9 Graphical Representation of Setpoints I Figure 9.8.1-1, Low Steam Line Pressure Safety Injection Setpoint (Existing)

I +Operability Limit (OL+) 538.0 psig (0.2537 Vdc)

I +As-Found (S) 537.6 psig (0.2536 Vdc)

I +As-Left (AL') 537.0 psig (0.2534 Vdc)

Field Trip Setpoint (FTSP) 530.0 psig (0.25 14 Vdc)

I -As-Left (AL-) 523.0 psig (0.2494 Vdc)

I -As-Found (AF) 522.4 psig (0.2492 Vdc)

I -Operability Limit (OL-) 522.0 psig (0.2491 Vdc)

I Existing Allowable Value (AV) 500 psig (0.2429 Vdc)

Limiting Trip Setpoint (LTSP) 458.97 psig Analytical Limit (AL) 320.3 psig

• cI ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 16 of 18 Figure 9.8.1-2, Low Steam Line Pressure Safety Injection Setpoint (EPU)

I +Operability Limit (OL') 553.0 psig (0.2580 Vdc)

I +As-Found (AF') 552.6 psig (0.2579 Vdc) 552.0 psig (0.2577 Vdc)

I Recommended Field Trip Setpoint (IEiTSP) 545.0 psig (0.2557 Vdc) (Proposed)

I -As-Left (AL-) 538.0 psig (0.2537 Vdc)

I -As-Found (AF) 537.4 psig (0.2535 Vdc)

I -Operability Limit (OL*) 537.0 psig (0.2534 Vdc)

Recommended Allowable Value (AV) 535.0 psig (0.2529 Vdc) (Proposed)

Limiting Trip Setpoint (LTSP) 533.97 psig Analytical Limit (AL) 395.3 psig

a C a ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 17 of 18 IMPACT ON PLANT DOCUMENTS As a result of this minor revision, the following plant documents should be revised as follows:

o 1ICP 02.001RD, "Reactor Protection and Engineered Safety Features Red Channel Analog 92 Day Surveillance Test" (See Attachment A for changes) 1ICP 02.001BL, "~eactorprotection and ~ n ~ i n e e r Safety ed Features Blue Channel Analog 92 Day Surveillance Test" (See Attachment A for changes) lICP 02.001WH, "Reactor Protection and Engineered Safety Features White Channel Analog 92 Day Surveillance Test" (See Attachment A for changes) s 1ICP 02.001YL7"Reactor Protection and Engineered Safety Features Yellow Channel Analog 92 Day Surveillance Test" (See Attachment A for changes) s 21CP 02.001-RD,"Reactor Protection and Engineered Safety Features Red Channel Analog 92 Day Surveillance Test" (See Attachment A for changes) s 21CP 02.001BL, "Reactor Protection and Engineered Safety Features Blue Channel Analog 92 Day Surveillance Test" (See Attachment A for changes) 21CP 02.001WH, "Reactor Protection and Engineered Safety Features White Channel Analog 92 Day Surveillance Test" (See Attachment A for changes) 21CP 02.001YL, "Reactor Protection and Engineered Safety Features Yellow Channel Analog 92 Day Surveillance Test" (See Attachment A for changes)

Q 1ICP 02.020RD, "Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes) s 1ICP 02.020BL, "Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes)

Q 1ICP 02.020WH7"Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes) o lICP 02.020YL, "Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes) 0 21CP 02.020RD7"Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes) 21CP 02.020BL7"Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes) 0 21CP 02.020WH, "Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes)

Q 21CP 02.020YL, "Post-Refueling Pre-Startup RPS and ESF Red Channel Analog Surveillance Test" (See Attachment A for changes) 0 Point Beach Nuclear Plant Technical Specifications, Section 3.3.2 and B3.3.2 For the EPU condition, change the Tech Spec Allowable Value to 535 psig in Table 3.3.2-1.

%CI1 ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: 18 of 18 PBNP Setpoint Document STPT 2.1, "Safety Injection", Rev. 2 For the EPU condition, change the Low Steam Line Pressure setpoint and Tech Spec Allowable Value to 545 psig and 535 psig, respectively.

11.0 ATTACHMENT LIST Same as Revision 4 of calculation PBNP-IC-39, except Attachment A (See the attached sheets for the changes).

12.0 10CFR50.59 REVIEW As a result of this minor revision, there are no documentation changes due to the existing plant condition. Therefore, a 10CFR50.59 review is not required.

Due to EPU condition, the Field Trip Setpoint (FTSP), Operability Limit (OL) and Technical Specification Allowable Values (AV) associated with the Low Steam Line Pressure Safety Injection were changed in this minor revision. NRC prior approval is required in order to implement the revised Technical Specifications values. Since a license amendment is already acknowledged to be required, no separate 50.59 review is necessary for revising the Technical Specification values. The present intent is to include the Technical Specification changes, identified as EPU changes in this calculation, for RPS and ESFAS setpoints in the Extended Power Uprate License Amendment Request.

Note that the EPU implementation, after the EPU license amendment is received from NRC, will require separate screening and possibly a full 50.59 evaluation of individual changes being made. For future EPU implementation, a separate 50.59 screening number (SCR 2008-178) and a separate 50.59 evaluation number (SE 2008-014) have been reserved.

ENGINEERING CONSULTANTS Calculation No: PBNP-IC-39 CALCULATION SHEETS Rev. No: 004-A Page: A1 of A1 ATTACHMENT A Same as Revision 4 of calculation PBNP-IC-39, except the following changes due to EPU condition:

For IDS l(2) PC-468AA3 and PC-483A/B: l(2) ICP 02.001RD and l(2) ICP 02.020RD For D s I(2) PC-478m and PC-482A/B: l(2) ICP 02.001BL and l(2) ICP 02.020BL For IDS l(2) PC-469AB: l(2) ICP 02.001WH and l(2) ICP 02.020WT-I For IDS l(2) PC-479AA3: l(2) ICP 02.001YL and l(2) ICP 02.020YL STEAM PROCESS OUTPUT (COMP STM PRESS)

GENERATOR SETPOINT SETPOINT AS- As-Found AS- As-Left Limiks Operability PRESSURE psig Vdc FOUND Limits LEFT Limits Vdc Low High Low High Low High Vdc Vdc Vdc Vdc Vdc Vdc

ENCLOSURE I NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 261, EXTENDED POWER UPRATE TRANSMIITAL OF SAMPLE CALCULATIONS FOR REACTOR PROTECTION SYSTEM IENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SETPOINT CALCUATIONS AITACHMENT 5 AUXILIARY FEEDWATER PUMPS LOW SUCTION PRESSURE SW SWITCHOVER UNCERTAINTYISETPOINT CALCULATION 86 pages follow

ISSUE

SUMMARY

Form SOP-0402-07, Revision 8 PROJECT NAME: EPU -AFW Minor revision to Calculation 97-0231 to support the changes to the TDAFW low suction pressure switchoverhip circuits in EC-13407.

DATE FOR RN.:

INPUTS1ASSUMPTIONS INPUTS1ASSUMPTIONS NOTE: PRINT AND SIGN IN THE SIGNATURE AREAS

./"

Calculation No .97-023 1 1'(

sarg~rrt

\

di~:~ n d y L L C Revision 002-C

..F' Table of Contents Page 2 of 72

1.0 BACKGROUND

, PURPOSE, AND SCOPE OF CALCULATION ............................4 1.1 Background ......................................................................................................... 4 1.2 Purpose .................................................................................................................. 4 1.3 Purpose of This Revision/ Revision History ......................................................... 5 1.4 Scope ....................................................................................................................... 6 1.5 Instrumentation Evaluated ................................................................................... 6 1.6 Superseded Station Calculations....................................................................... 6 2.0 ACCEPTANCE CRITERIA ........................................................................................ 7 3.0 ABBREVIATIONS ........................................................................................................... 8

4.0 REFERENCES

.................................................................................................................. 9 4.1 General ................................................................................................................. 9 4.2 Drawings .............................................................................................................. 9 4.3 E~ncedures ............................................................................................................10 4.4 Vendor ............................................................................................................. 10 4.5 Calculations....................................................................................................... 11 5.0 ASSUMPTIONS.............................................................................................................. 12 5.1 Validated Assumptions .................................................................................... 12 6.0 DESIGN INPUTS ........................................................................................................... 14 6.1 Loop Definitions .............................................................................................. 14 6.2 Loop Block Diagram .......................................................................................... 14 6.3 Component Models and Tag Numbers .............................................................. 15 6.4 Transmitter Operating Spans ......................................................................... 15 6.5 Environmental Considerations .......................................................................... 16 6.6 Analytical Limit .................................................................................................... 18 7.0 METHODOLOGY ......................................................................................................... 20 7.1 Uncertainty Determination ............................................................................... 20 7.2 As-Found Tolerance Equation Summary ..........................................................24 7.3 As-Left Tolerance Equation Summary ............................................................. 25 7.4 Calculated Setpoint (SP) Equation Summary ................................................. 26

Calculation No .97-023 1 Revision 002-C Table of Contents Page 3 of 72 8.0 BODY OF CALCULATION .........................................................................................27 8.1 Device Uncertainty Analysis ................................................................................ 27 8.2 Process Error (PE) .............................................................................................. 49 8.3 Device Uncertainty Summary .......................................................................... 50 8.4 Total Loop Error .................................................................................................. 53 8.5 Acceptable As-Found and As-Left Calibration Tolerances .............................55 8.6 Setpoint Evaluation ............................................................................................. 60 9.0 RESULTS AND CONCLUSIONS, WITH LIMITATIONS ...................................... 65 9.1 Loop Uncertainties ........................................................................................... 65 9.2 Field and Calculated Switchover/Trip Setpoint (FTSPISP) .............................65 9.3 Acceptable As-Left and As-Found Tolerances .................................................. 66 9.4 Limitations ............................................................................................................ 66 9.5 Gra.pk.icstl-Representationof Revised Setpoints and Tolerances ..................... 68 10.0 IMPACT ON PLANT DOCUMENTS .......................................................................... 71 11.0 ATTACHMENT LIST ................................................................................................... 72

Calculation No.97-023 1 Revision 002-C

,.,' Page 4 of 72

1.0 BACKGROUND

, PURPOSE, AND SCOPE OF CALCULATION 1 . Background ECs 13400 through 13407 install new MDAFW pumps, modify controls for the existing TDAFW pumps, and convert the existing MDAFW pumps to Standby Steam Generator (SSG) feed pumps. The SSG feed pumps are used in normal startup and shutdowns, receive no automatic start signals and are tripped on signals that would automatically initiate AFW flow.

The new MDAFW pumps will have their own connection to the Condensate Storage Tanks. This connection will be separate from the TDAFW pumps connection to the Condensate Storage Tank.

The Auxiliary Feedwater (AF) System automatically supplies feedwater to the steam generators to remove decay heat from the Reactor Coolant System upon a loss of normal feedwater supply. The AF system consists of two independent pump systems per unit; Motor Driven (MD) AFPs (1P-53 and 2P-53, and steam turbine-driven (TD) AFPs (1P-29 and 2P-29).

The nonnal source of water for the AFPs is the Condensate Storage Tank (CST), and the safety-related supply is the Service Water (SW). The switch from the normal suctibn supply to the safety related supply is done automatically or manually.

A pressure transmitter is installed on the suction side of each AF pump that monitors AFP suction pressure. This pressure transmitter will provide a signal that initiates the switch to the safety related supply, or subsequently, trips the pump on low suction pressure if the switchover was not successfid. Additionally, an alarm will actuate prior to a triplswitchover to annunciate (in the Main Control Room) that the process is approaching a low suction pressure condition.

The low-low suction pressure switchoverlpump trip and low suction alarm functions associated with each AFP are provided by setpoint-controlled bistable units downstream of the Low Suction Pressure Transmitter, which provide switchoverltrip and alarm output. The output of the low-low switchoverltrip bistable (but not the low alarm) is connected to a Time Delay Relay (TDR). The output of the bistable is delayed in order to minimize spurious switchoversltrips caused by nonnal transient drops in suction pressure during plant startup. The time delay function for the low suction pressure switchoverltrip is evaluated in Calculation 97-021 1, "AFW Pump Low Suction Pressure Trip Time Delay Relay Uncertainty Calculation".

The AF pump low low suction pressure supply switchover is a safety-related function.

1.2 Purpose The purpose of this minor revision is to determine the instrument uncertainties, Low Suction Pressure Alann Setpoint, and Low Suction Pressure Switchover/Pump Trip Setpoint associated with the Turbine-Driven Auxiliary Feedwater Pump (TDAFP) Low Suction Pressure Switchover/Trip instrument loop.

Calculation No.97-023 1 Revision 002-C Page 5 of 72 A separate minor revision (Revision 002-D) has been prepared to evaluate the MDAFW pump low suction pressure switchoverltrip and alarm uncertainties and setpoints.

The low suction pressure trip circuits for the Standby Steam Generator (SSG) pumps (P38AIP38B) are not modified. Uncertainties and setpoints for these circuits detennined in parent Revision 2 of this calculation remain valid until the system transition to SSG pumps in EC-13407.

Because the Low Suction Pressure SwitchoverITrip is a safety-related function and is required to operate duringlafter a design basis event, this calculation will determine uncertainties for accident environmental conditions.

The results of this calculation, along with the results of Calculations97-021 1 and PBNP-IC-42, are used as input to Calculation 97-0215 to ensure that sufficient water (including water pumped during the switchoverltrip time delay) is available to supply the AFPs to allow an orderly switchover to the safety related supply, or autolnatically trip if the switchover is unsuccessful following a loss of CSTs, thus preventing damage to the pump (See Section 10.0).

Purpose of This ~evisionlRevision History Puruose of Minor Revision This minor revision (-002C) suppol-tsthe lnodifications to the TDAFW low suction pressure switchoverltrip circuits in EC-13407.

The existing TDAFW triplalam and indication will split into two loops by EC 13407:

Narrow-range Low Low SW Switchover/Pump TripITrip Almn and Low Alarm scaled from 0-30 psig (Sections 5.1.5 and 9.4.6).

e Suction pressure indication scaled from 0-100 psig (Sections 5.1.5 and 9.4.6).

Since the suction pressure indication loops are not Reg. Guide 1.97 Cat 1 Type A variables and since they are no longer a part of the suction pressure trip alarms circuits, their uncertainties and setting tolerances are not addressed in this minor revision.

Moreover, the parallel instnunentation legs fed by the pressure transmitters (e.g. control board indication and PPCS input) were not addressed in previous revisions of this calculation, and therefore will not be addressed by this minor revision.

Revision Histon, Minor Revision -002B was originally issued during June of 2009 to support the EPU LAR Submittal. This minor revision determined the setpoint for "AFW Pump Suction Transfer on Suction Pressure Low", which was taken as input into EPU Tech Spec Section 3.3.2.

Calculation No.97-023 1 Revision 002-C Page 6 of 72 As with Minor Revision -002B, this minor revision (-002C) supports the modifications to the TDAFW low suction pressure switchover/trip circuits in EC-13407. However, this minor revision includes updates to correct the following:

o Eliminates the use of the uncertainty reduction factor for setpoints with a single side of interest. This change will result in a new Setpoint for "AFW Pump Suction Transfer on Suction Pressure Low", which must be incorporated in EPU Tech Spec Section 3.3.2.

• Incorporates lessons learned regarding M&TE accuracy for the Fluke 45 multimeter.

This minor revision supersedes minor revision -002B in its entirety.

1.4 Scope The scope of this calculation is listed below:

9 Detennine uncertainties for the TDAFP Suction Pressure Switchover/Trip Instnunentation (excluding Time Delay Relay).

9 Evaluate the Low Suction Pressure Alarm setpoint and the Low-low Suction Pressure Switchover/Trip Setpoint for the TDAFP (l(2)P-29).

9 Detennine Acceptable As-Found / As-Left Calibration Tolerances for TDAFP Suction Pressure Instrumentation.

1.5 Instrumentation Evaluated This calculation evaluates the plant equipment listed in the table below (with the exception of the pumps). See Sections 6.2, 6.3 and 6.4 of this calculation for instrument specifications, parameters, ranges and loop configurations.

Table 1.5-1: Instrumentation List Current-to- Voltage-to- Switchover &

Pressure Pump Voltage Current Trip / Alarm Transmitter Converter Converter Bistable 1P-29 IPC-4044-L 1PT-4044A IPQ-4044 1PM-4044-3 driven 1PC-4044-LL 2P-29 2PC-4044-L 2PT-4044A 2PQ-4044 2PM-4044-3 driven 2PC-4044-LL 1.6 Superseded Station CaIcuIations This minor revision supersedes minor revision 97-023 1-002-B in its entirety.

Calculation No. 97-0231 Revision 002-C Page 7 of 72 2.0 ACCEPTANCE CRITERIA This calculation determines the following:

The adequacy of Liiniting Trip Setpoints (LTSP) for the TDAF Low-Low Suction Pressure Pump SwitchoverITrip as added by the Extended Power Uprate The LTSP is acceptable if the following criteria are met:

The calculated setpoint (SP) is established to ensure that the instrument channel pump trip initiation, is., actuation of the Time Delay Relay (see Calculation 97-021 1) occurs before the AL is reached. The SP will be compared to the LTSP to ensure that the LTSP I SP (for increasing process) or the LTSP 2 SP (for decreasing process).

0 The adequacy of existing Field Trip Setpoints (FTSP) for the TDAF Low-Low Suction Pressure P u p SwitchoverITrip as added by the Extended Power Uprate The FTSP is acceptable if the following criteria are met:

The calculated setpoint (SP) is established to ensure that the instrument channel pump trip initiation, is., actuation of the Time Delay Relay (see Calculation 97-0211) occurs before the AL is reached. The SP will be coinpared to the FTSP to ensure that the FTSP I SP (for increasing process) or the FTSP 2 SP (for decreasing process). In addition, the FTSP must provide sufficient margin to ensure that the LTSP is protected.

0 The adequacy of existing Field Trip Setpoints (FTSP) for Low Suction Pressure Pump Alann The FTSP is acceptable if the following criteria are met:

1) The SP will be compared to the FTSP to ensure that the FTSP I SP (for increasing process) or the FTSP 2 SP (for decreasing process).

2) The FTSP is 0.5 psig above the AFP Low-Low Suction Pressure SwitchoverlTrip Setpoint Uncertainties for the AFP Suction Pressure Instrumentation All uncertainty results are deemed acceptable so long as they are calculated in accordance with Point Beach Nuclear Plant's Instrument Setpoint Methodology (Ref. G. 1). Any deviations from this methodology are noted where applicable.

Note: All setpoints in this calculation are for decreasing process values.

Calculation No.97-023 1 Revision 002-C Page 8 of 72 3.0 ABBREVIATIONS AL Analytical Limit AF Auxiliary Feedwater AFP Auxiliary Feedwater Pump AV Allowable Value BAF Bistable As-Found Tolerance BAL Bistable As-Left Tolerance COT Channel Operational Test CST Condensate Storage Tank EOP Emergency Operating Procedures FSAR Final Safety Analysis Report FTSP Field Trip Setpoint IVAF Current-to-Voltage Converter As-Found Tolerance IVAL Current-to-Voltage Converter As-Left Tolerance LSSS Limiting Safety System Setting LTSP Limiting Trip Setpoint M&TE Measurement and Test Equipment NPSH Net Positive Suction Head PBNP Point Beach Nuclear Plant PL Process Limit PS Process Span PT Pressure Transmitter (Section 6.6) Pressure Tester (remainder of calc)

RAD Radiation Absorbed Dose SAF Sensor As-Found Tolerance SAL Sensor As-Left Tolerance SP Calculated Setpoint SW Service Water SRSS Square Root of the Sum of the Squares SSG Standy Steam Generator TLE Total Loop Error URL Upper Range Limit w Voltage-to-Current Converter As-Found Tolerance VIAL Voltage-to-Current Converter As-Left Tolerance

Calculation No.97-023 1 Revision 002-C Page 9 of 72

4.0 REFERENCES

The revisions andlor dates of the References per this section are current as of 6/2/2010.

4.1 General G. 1 Point Beach Nuclear Plant Design & Installation Guidelines Manual DG-101, "Instrument Setpoint Methodology", Rev. 5 G.2 Bechtel Corporation Specification No. 61 18-M-40, Rev. 1, "Specification for Heating, Ventilating, and Air Conditioning Controls."

G.3 WCAP-8587, Rev. 6-A, "Methodology for Qualifying Westinghouse WRD Supplied NSSS Safety Related Electrical Equipment", dated March 1983 G.4 Point Beach Nuclear Plant FSAR:

o Section 9.8.1 (dated 2010) o Section 9.5 (dated 2010) e Section 11.6.2 (dated 20 10)

G.5 Not used.

G.6 Walkdown, Pressure Transmitter Elevation and Pressure Tap Elevation (Attachment A)

G.7 ASME Steam Tables for Industrial Use (Version 1997), Copyright 2000.

G.8 PBF-2032, Rev. 92, "Operations Daily Logsheet" G.9 WE Letter NPC-28077 to NRC, "Response to NUREG-0737", dated 9/14/81 G. I0 Letter NRC 200-0030, dated April 7,2009, "License Amendment 26 1, Extended Power Uprate" G. 11 Walkdown, ICTI-62 1 and ICTI-797 Readability (Attachment C) 4.2 Drawings D.l Bechtel6118, Dwg. M-217, Sht. 1, Rev. 87, "P&LD Auxiliary Feedwater System", Point Beach N.P., Unit 1&2 D.2 Bechtel6118, Dwg. M-217, Sht. 2, Rev. 22, "P&D Auxiliary Feedwater System", Point Beach N.P., Unit 1&2 D.3 Foxboro 62550, Dwg. CD1-15, Rev. 0, "Point Beach N.P., Unit 1 Connection Diagram - Rack 1C171B-F/1C197"

Calculation No.97-023 1 Revision 002-C Page 10 of 72 D.4 Foxboro 62550, Dwg. CD2-15, Rev. 1, "Point Beach N.P., Unit 2 Connection Diagram - Rack 2C173B-F/2C-197" D.5 Not Used D.6 Not Used D.7 977-82, Sheet 10, Rev. 9, "Cable Spreader Room Air Conditioning System Rack C58" (available in Passport as 0082).

4.3 Procedures P. 1 lICP 04.003-5, Rev. 13, "Auxiliary Feedwater Flow and Pressure Instruments Outage Calibration", 8/30/05 P.2 21CP 04.003-5, Rev. 15, "Auxiliary Feedwater Flow and Pressure Instruments Outage Calibration", 8/30/05 P.3 1ICP 04.032-1, Rev. 16, "Auxiliary Feedwater. System and Charging Flow Electronic Outage Calibration", 11/15/05 P.4 21CP 04.032-1, Rev. 13, "Auxiliary Feedwater System and Charging Flow Electronic Outage Calibration", 11/15/05 P.5 Not Used.

P.6 Not Used.

P.7 ICI 12, Rev. 9, "Selection of M&TE for Field Calibrations" 4.4 Vendor V.l Not Used.

V.2 Foxboro Spec 200 Composite Manual, PBNP VTM # 00580, Rev. 8, Foxboro Technical Information, TI 2AI-130, dated October 1977, "Current-to-Voltage Converters" V.3 Foxboro Spec 200 Composite Manual, PBNP VTM # 00580, Rev. 8, Foxboro Technical Information, TI 2AO-130, dated October 1977, "Voltage-to-Current Converters, Model 2AO-VAI, Isolated, 4 to 20 mnAdc, Adjustable Span & Zero" V.4 Foxboro Spec 200 Composite Manual, PBNP VTM # 00580, Rev. 8, Foxboro Technical Information, TI 2AP-100, dated March 1977, "Spec 200 Nest Alarms" V.5 Johnson Controls Temperature Composite Book 2, VTM # 00309B, Rev. 5, dated 8/15/94 - T-4000 Series Pneumatic Room Thermostats (Tab - Thermostats

& Thermometers).

Calculation No. 97-0231 Revision 002-C Page 11 of 72 V.6 User Guide HP 34401A Multirneter, VTM 01692, Rev. 0 V.7 Rose~nountModel 3051N Smart Pressure Transmitter for Nuclear Service, Reference Manual 00809-0100-4808, Rev. CAYJune 2008, PBNP VTM # 01826.

V.8 Fluke 45 Dual Display Meter User Manual, VTM 01425, Rev 1 4.5 Calculations C.l Calculation 97-0172, Rev. 2, "Available Water in Volume of Piping to the Auxiliary Feedwater Pumps Following Pipe Break at Elevation 25-6" C.2 Calculation 2003-0062, Rev. 2, "AFW Pump NPSH Calculation and Condensate Storage Tank Required Fluid to Prevent Vortexing.", including 2003-0062-002-A and 2003-0062-002-B.

C.3 Calculation No. M-8992-02.TM7 "Thennal Modes Evaluation Report for Point Beach-Units 1&2",Appendix L, Rev. 1

Calculation No. 97-0231 Revision 002-C

,,,A; Page 12 of 72 5.0 ASSUMPTIONS 5.1 Validated Assumptions 5.1.1 It is assumed that the environmental conditions in the Auxiliary Feedwater Pump Room (in the Control Building) are similar to the conditions inside the Auxiliary Building.

Basis: Section 2.1 of Bechtel Specification 6 118-M-40 (Ref. G.2) does not specifically identify environmental conditions for the Auxiliary Feedwater Pump Room. Descriptions of the various plant W A C systems and their controls are provided in Section 3.0 of Ref. G.2. A comparison of the description of the AF Pump Room ventilation to that of the areas listed in Section 2.1 indicates that the air conditioning features make this area comparable to the Auxiliary Building.

Also, a review of PBF-2032 Daily Logsheet, (Ref. G.8) verifies that the maximum temperature inside the Auxiliary Feedwater Pump Room is the same as the maximum temperature inside the Auxilialy Building.

5.1.2 It is assumed that the maximum temperature (for accident conditions) in the Auxiliary Feedwater Pump Cubicle Area is 120 OF.

Basis: Table 6-1 of WCAP-8587 (Reference G.3) states that "abno~maloperzting parameters" apply to areas outside of containment when the HVAC System is non-safety related, resulting in a maximum temperature of 120 OF and humidity of 95%.

The Auxiliary Feedwater Pump Area HVAC system is non-safety related (Per Section 9.5 of Ref. G.4). Therefore, 120 OF is used as the maximum operating temperature in the Auxiliary Feedwater Pump Cubicle Area.

5.1.3 It is assumed that the maximum environmental temperature of the Control Room and Computer Room instrumentation is 120 O F .

Basis: Table 6-1 of WCAP-8587 (Reference G.3) states that when the HVAC is non-safety related, a temperature of 120 OF (loss of chiller) should be used. Since the Control Room and Computer Room HVAC System chiller is not powered from an essential power bus, the Control Room and Computer Room W A C System is considered a non-safety related system.

Calculation No.97-023 1 Revision 002-C Page 13 of 72 5.1.4 It is assumed that the setting tolerances for the instrulnents evaluated in this calculation are as indicated in the tables below:

I Steam Driven Pump Suction Pressure Instrumentation I Switchover & Trip I Alarm Pressure Bistable units I N Converters V/I Converters Transmitters 1(2)PC-4044-LL l(2)PQ-4044 l(2)PM-4044-3 1(2)pc-4044-~

l(2)PT-4044A (Switchover I (Alarm)

Trip)

I f 0.04 mAdc I f 0.050 Vdc 1 f 0.08 mAdc 1 f 0.020 Vdc / f 0.03 mAdc I Basis: These setting tolerance values have historically provided acceptable instmnent performance and consistency in the calibration program for similar instnunents installed throughout the plant. These values are routinely achievable for the installed inshuments, and are consistent with safety limits and test equipment capability. They are currently used in practice at the station, and ilnplemented by calibration procedures P. 1 - P.4. As-Found setting tolerances are to be determined in this calculation (see Section 8.5).

5.1.5 It is assumed that all impacted equipment will be created or modified to incorporate the changes per EC-13407 and minor revisions of this calculation.

Basis: This minor revision creates an imposed condition for EC 13407 to install the pressure transmitters 1PT-4044A and 2PT-4044A which will function as the narrow-range low suction switchover/pump trip/alarm pressure transmitters. The transmitters installed by EC 13407 replace the pump trip and alann functionality of existing transmitters (1PT-4044 and 2PT-4044) ranged from 0 - 100 psig with transmitters ranged from 0-30 psig to recapture uncertainty in order to provide the required CST level and have significant margin in the water volume. The existing transmitters 1PT-4044 and 2PT-4044 are required to provide indication.

The results of this calculation are only valid upon installation of the steam driven pump suction pressure instnunentation according to the changes doculnented in EC 13407 and this minor revision.

Calculation No. 97-0231 Revision 002-C Page 14 of 72 6.0 DESIGN INPUTS 6.1 Loop Definitions The AFP Suction Pressure Instrumentation Loops that are analyzed in this calculation are shown in block diagram format in the figures (below), and are explained in more detail in Sections 6.2 and 6.3.

6.2 Loop Block Diagram The block diagram below (Fig. 6.2-1) shows the component configuration for the AF loops addressed in this calculation. The block diagram below (Fig. 6.2-2) shows the component configuration for the AF loops in the previous revisions of this calculation.

Although not addressed in this calculation, the time delay relay that succeeds the SW switchover suction pressure bistable in each loop is shown for completeness (these time delay relays are addressed in 97-0211, "AFW Pump Low Suction Pressure Trip Time Delay Relay Uncertainty Calculation"). Other parallel instrumentation legs fed by the pressure transmitters (e.g. control board indication and PPCS input) are not shown, as they are not involved in the Low Suction Pressure Switchover/Alarm/Trip functions addressed in this calculation.

Figure 6.2-1 Steam Driven AF Pump Low Suction Pressure Instrumentation Post EC 13407 I

I . I I

Current -to - Voltage -to - I I I Suction Transmitter Voltage Converter " Current Converter I

/*

Bistable l ( 2 ) PC - 4044 -L m-l(2)PQ-4044 1(2)PM -4044 -3 I I Lo Alarm 1I I LOW-LOW Suction Bistable t m- Pressure Trip 1 (2) PC - 4044 -LL I AFW Pump Cubicles I I Low-Low Trip (Control Building) I Alarm I

Computer Room I Contml Room Delay I+m-SwitchoverlTrip Logic I

1 Relay 1(2)62-4044A j

I f

I

Calculation No.97-023 1 Revision 002-C Page 15 of 72 Figure 6.2-2 Steam Driven AF Pump Low Suction Pressure Instrumentation Prior to EC 13407 I I I

Current -to- Voltage -to- I I

I Suction Voltage Current Bistable I Transmitter 1( 2 ) PT-4044A Converter 1(2)PQ -4044 Converter 7 I 1 ( 2 ) P C -4044 -L

/

B- Pressure Lo A l a n 1 ( 2 ) P M -4044 -3 1 I

I 1

I  !

i

,Low-Low Suction Bistable 1( 2 ) PC - 4044 -LL r

/

I

- PressureTrip A W Pump Cubicles I Lo-Lo Trip

( Conbol Building ) i Aiarnl i I I Computer Room I Control Room I

I I

6.3 Component Models and Tag Numbers The following table identifies each component shown in Figures 6.2-1 for the AFW Pump Low Suction Pressure SwitchoverITrip instrument loops, and provides the associated equipment information for use throughout this calculation.

Table 6.3-1: Steam Driven AF Pump Suction Pressure Instrumentation Component Model Equipment Tag Referenee(s)

Number Rosemount V.7,D.3,D.4 Transmitter l(2)PT-4044A 305 lNG3A02Al JH2B2 Loop Power Supply /

Current-to-Voltage Foxboro N-2AI-12V l(2)PQ-4044 D.3, D.4 Converter Voltage-to-Current 1(2)PM-4044-3 D.3, D.4 Foxboro N-2AO-VAI Converter Foxboro 1(2)PC-4044-L Bistable Units D.3, D.4 N-2AP+ALM-AR 1(2)PC-4044-LL 6.4 Transmitter Operating Spans The calibrated transmitter range is 0 - 30 psig (Sections 5.1.5 and 9.4.6). The output is a 4-20 lnAdc signal (References P.l and P.2). The Upper Range Limit (URL) is 1000 inH20 (Ref. V.7). The conversion factor from psig to inH20 is determined at 68 O F and 14.7 psia. This is consistent with the standard temperature and pressure used for calibration.

Converting the URL fkom inH20 to psig:

Where 1 psig = 27.729 inH20 URL = 1000 inH20 * (1 psig / 27.729 inH20)

URL = 36.063 psig

Calculation No.97-023 1 Revision 002-C Page 16 of 72 6.5 Environmental Considerations Per Ref. G.9, the AF Pump Suction Pressure Trip instrumentation loops are required to trip the corresponding AF Pump when suction pressure is inadequate. This is a pump protection feature used to control switchover fi-orn the normal AFP Supply (Condensate Storage Tank) to the alternative supply (Service Water). This function is safety related.

The associated Low Suction Pressure Alarm function is not safety related. However, this calculation conservatively treats this function as safety related also.

6.5.1 Control Building (Auxiliary Feed Pump Room)

As shown in Figure 6.2-1 (and per References P.l- P.4), the Steam Driven Pump Suction Pressure transmitters and rack components (except for 1(2)PC-4044-L) are located in the AF Pump Cubicles in the Control Building.

Accident Conditions The minimum design temperature for the Auxiliary Building HVAC system (per Section 3.9.h of Ref. G.2)-is 60 OF during winter. Therefore, per Assumption 5.1.1, 60 OF is taken as the mninknurn temperature for the Control Building Aux.

Feed Pump Cubicle area.

Per Assumption 5.1.2, accident conditions in the Aux. Feed Pump Cubicle area will not exceed a temperature range of 120 OF, and a maximum relative humidity of 95%. Therefore, a maximum temperature of 120 OF and a maximum humidity '

of 95% are used for accident environmental conditions in this area.

While the Aux. Feed Pump Cubicle area is subject to the accident conditions described in the previous paragraph, these accident conditions do not include elevated radiation levels, as this area is not part of the Radiologically Controlled Area (RCA) at the station. Therefore, the 40-Year Dose of less than 400 RADs -

taken for Normal Conditions - is also applicable to accident environmental conditions for the Aux. Feed Pump Cubicle area.

Table 6.5-1: Aux. Feed Pump Cubicle Area Environmental Conditions Minimum Maximum Humidity Radiation Conditions Temp. Temperature

(%) (Ws)

("F) ("PI Accident 60 120 95 Less than 400 (40-year dose) 6.5.2 Main Control Room /Computer Room The Foxboro Spec 200 rack that contains the Low Pressure Alarm Bistable (l(2)PC-4044-L) for the Steam Driven Pumps is located in the Computer Room (Per References P.3 - P.4).

Calculation No.97-023 1 Revision 002-C Page 17 of 72 The Control Room W A C System controls the temperature of the Control Room and the Computer Room at 75 OF per Ref. G.2. Per Reference G.4, the temperature can vary +/-I0 OF, resulting in a minimum temperature of 65 OF.

This temperature variation is supported by the fact that the Johnson Controls T-4002-202 thermostat (Ref. D.7) in the Control Room is capable of controlling the room temperature (Ref. V.5) within these bounds. In accordance with Section 3.3.4.7 of Reference G.l, a minimum temperature of 65 OF is chosen for the components in the Main Control Room and Computer Room.

Per Assumption 5.1.3, a maximum Control Room /Computer Room temperature of 120 OF is chosen for the subject instrument loops. This maximum temperature corresponds to enviromnental conditions associated with a loss of the Control Room HVAC cooling unit. The choice of this maximum temperature is justified by the intended function of the AF Pump Suction Pressure Switchover/Trip (i.e.

this function is safety related, and is required to operate correctly under compromised environmental conditions caused by a loss of the W A C cooling unit).

The Control Room humidity of 95 % (95% R.H. due to loss of W A C chiller) is documented in Table 6-1 of Ref. G.3.

FSAR Section 11.6.2 (fifth paragraph) (Ref. G.4) states that the Control Room is in Zone I and Table 11.6-1 states the maximum dose rate in Zone I is 1.0 mrem/hr .

Table 6.5-2: Control Room Environmental Conditions Min. Max.

Humidity Radiation Temperature Temperature Safety Related (OF) (OF) (YO) (mremlhr) 65 120 95 1.O

Calculation No.97-023 1 Revision 002-C Page 18 of 72 6.6 Analytical Limit The elevation in the Auxiliary Feedwater (AF) pump suction pipe at which the low suction pressure alann Iswitchoverltrip initiation will occur, i.e., actuation of the Time Delay Relay (see Calculation 97-0211) can be determined by the following equation:

EL Trip = (P Trip

• CF) + EL PT where:

EL Trip = Elevation in the AF pump suction piping where switchoverltrip initiation must occur.

P Trip = Corresponding AF pump low suction switchoverltrip initiation pressure.

CF = Conversion factor from fluid height (ft) to pressure (psig).

EL PT = Elevation of the AF pump suction pressure transmitters.

The Analytical Limit (AL) is the minimum pressure at which the switchoverltrip initiation-(actuatioc-ofthe Timne Delay Relay) must occur. This value is also considered P Trip. Therefore, rearranging the above formula to solve for the pressure trip setpoint (P Trip) detennines the Analytical Limit:

144in.*

AL = P Trip = (EL Trip - EL PT) 1CF; where CF = vro. .f tz Note: The conversion factor (CF) from fluid height to pressure is determined at 40 OF and 14.696 psia. This will result in the most conservative (higher) trip pressure setpoint (Reference G.7).

The AF Pwnp low suction pressure switchoverltrip perfonns two functions:

1) To protect the pump from low NPSH conditions, and

2) To protect the pump from a loss of suction.

Calculation 2003-0062 (Reference C.2) determines that the lowest possible water level (NPSH) for the AF system is El. 19.8 feet. This height can be considered as the elevation at which the pump protection trip must occur, or EL Trip, to protect the pump from low NPSH conditions.

Calculation 97-0172 (Reference C.l) detennines that, in the case of a seismic or tornado induced failure of the suction pipe, a linimnum volume of 5 12 gallons in the protected piping (corresponding to El. 24.17 feet) is available to maintain protection to the AF pumps. This elevation in the AF piping is selected as the point where the switchoverltrip initiation must occur. The minimum volume in the protected piping corresponding to EL 24.17 ft is used as an input to Calculation 97-02 15 for ensuring that sufficient water (including water pumped during the associated switchover and trip time delays) is available to supply the AFPs until they automatically switchoverltrip, thus preventing damage to the pwnp (See Section 10.0).

Calculation No.97-023 1 Revision 002-C Page 19 of 72 The bounding analytical limit for the pwnp suction switchover/trip initiation is:

EL Trip = 24.17 ft Transmitter Elevation Per Reference G.6:

EL IPT 4044 = 12.08 ft.

EL 2PT 4044 = 12.46 ft.

1(2)PT4044A will be installed at the same elevation as existing transmitters l(2)PT-4044 under ECN-15053 (EC 13403).

Note: Because the elevation of the pressure transmitter (EL PT) is subtracted from the elevation of the switchover/trip (EL Trip), and instrument loop initiates action on decreasing signal (pressure),selecting the lowest elevation will result in a larger difference in height, thus-generatinga larger pressure value thereby ensuring a more conservative value . Therefore, the Analytical Limit is calculated only for the height of 12.08 ft. The generated value is conservatively utilized for all transmitters. Also, fiiction drop associated with theAnalytica1 Limit creates a conservative (early) switchover/trip initiation and is therefore ignored in this calculation.

Substituting from above:

P Trip = (EL Trip - EL PT) / CF; (Reference G.7)

P Trip = (24.17 fk- 12.08 ft) / (CF); CF = 2.30674 ft-in '/lb P Trip = (12.09 ft) / (2.30674 ftlpsig) CF = 2.30674 ft/psig P Trip = 5.241 psig From above, P Trip is equal to the Analytical Limit. Therefore:

AL = 5.241 psig

Calculation No.97-023 1 Revision 002-C Page 20 of 72 7.0 METHODOLOGY 7.1 Uncertainty Determination The uncertainties and loop errors are calculated in accordance with Point Beach Nuclear Plant's Instrument Setpoint Methodology, DG-I01 (Ref. G.1). This methodology uses the square root of the sum of the squares (SRSS) method to combine random and independent errors, and algebraic addition of non-random or bias errors. Clarifications to this ~nethodologyare noted below:

A) Treatment of 95/95 and 75/75 Values The use of 95/95 values versus 75/75 values is dependent upon the instrument loop's category" as defined by Section 3.1 of Ref. G. 1. Per Section 3.1 of Reference G. 1, the devices evaluated in this calculation are classified as Category A - "RPS / ESF Technical Specification Setpoint Instrument loops and RG 1.97 Type A". This classification corresponds to a loop uncertainty expressed as a 95/95 value (95% probability at a 95% confidence level).

Based on the Category A classification (and based on the significance of the suction pressure switchover/trip hction), the total loop uncertainty will be reported as a 95/95 value.

B) Treatment of Significant Digits and Rounding This uncertainty calculation will adhere to the rules given below for the treatment of numerical results.

1. For values less than lo2, the rounding of discrete calculated instrument uncertainties (e.g. reference accuracy, temperature effect, etc.) should be performed such that the numerical value is restricted to three (3) or less digits shown to the right of the decimal point.

For example, an uncertainty calculated as 0.6847661 should be listed (and carried through the remainder of the calculation) as 0.685.

An uncertainty calculated as 53.235487 should be listed (and carried through the remainder of the calculation) as 53.235.

2. For values less than lo3,but greater than or equal to lo2,the rounding of discrete calculated instrument uncertainties (e.g. reference accuracy, temperature effect, etc.) should be performed such that the numerical value is restricted to two (2) or less digits shown to the right of the decimal point.

For example, an uncertainty calculated as 131.6539 should be listed (and carried through the remainder of the calculation) as 131.65.

Calculation No.97-023 1 Revision 002-C Page 2 1 of 72

3. For values greater than or equal to lo3, the rounding of discrete calculated insti-u~nentuncertainties (e.g. reference accuracy, temperature effect, etc.)

should be performed such that the numerical value is restricted to one (1) or less digits shown to the right of the decimal point.

For example, an uncertainty calculated as 2251.4533 should be listed (and camed through the remainder of the calculation) as 2251.5.

4. For Total Loop Uncertainties, the calculated result should be rounded to the numerical precision that is readable on the associated loop indication or recorder. If the loop of interest does not have an indicator, the Total Loop Error should be rounded to the numerical precision currently used in the associated calibration procedure for the end device in that loop (e.g. trip unit or alarm unit).

5. For calibration tolerances, the calculated result should be rounded to the numerical precision cul-rently used in the associated calibration procedure.

These rules are intended to preserve a value's acc1wacy,while minimizing the retention of insignificant or meaningless digits. In all cases, the calculation preparer shall exercise judgment when rounding and carrying numerical values, to ensure that the-values are kept practical with respect to the application of interest.

C) Seismic Considerations (Seismic versus Harsh Environment)

Per Reference C. 1, the AF Pump Suction Pressure Transmitters are designed to detect a loss of pump supply water source due to a piping failure, caused by a seismic or tornadic event. Therefore, this calculation considers seismic plant conditions.

Per Reference G. 1, Section 3.3.3.10, harsh environments associated with accident /

post-accident conditions are not considered coincident to a seismic or tornado event. However, in the case of the AF Pump Suction Pressure Instrument loop, a pump trip protects a safety-related function f?om a non-safety related piping failure. Since the non-safety related section of AF piping cannot be relied upon to function in the event of an accident, it is reasonable to consider a non-safety related piping failure during or after an accident.

Therefore, this calculation takes exception to Section 3.3.3.10 of Reference G.1 and considers harsh environmental conditions coincidental to a seismic or tornado event.

Calculation No.97-023 1 Revision 002-C Page 22 of 72 7.1.1 Sources of Uncertainty Per Reference G.l, the device uncertainties to be considered for accident and adverse (seismic event) environmental conditions include the following:

Sensor Accuracy Sensor Drift Sensor M&TE Sensor Setting Tolerance Sensor Power Supply Effect Sensor Temperature Effect Sensor Humidity Effect Sensor Radiation Effect Sensor Seismic Effect Sensor Static Pressure Effect Sensor Overpressure Effect Current-to-Voltage Converter Accuracy Current-to-Voltage Converter Drift Current-to-Voltage Converter M&TE Current-to-Voltage Converter Setting Tolerance Current-to-Voltage Converter Power Supply Effect Current-to-Voltage Converter Temperature Effect Current-to-Voltage Converter Humidity Effect Current-to-Voltage Converter Radiation Effect Current-to-Voltage Converter Seismic Effect Voltage-to-Current Converter Accuracy Voltage-to-Current Converter Drift Voltage-to-Current Converter M&TE Voltage-to-Current Converter Setting Tolerance Voltage-to-Current Converter Power Supply Effect Voltage-to-Current Converter Temperature Effect Voltage-to-Current Converter Humidity Effect Voltage-to-Current Converter Radiation Effect Voltage-to-Current Converter Seismic Effect Bistable Accuracy Bistable Drift Bistable M&TE Bistable Setting Tolerance Bistable Power Supply Effect Bistable Temperature Effect Bistable Humidity Effect Bistable Radiation Effect Bistable Seismic Effect Process Error (PE)

Bias Terms (Bias)

Per Section 3.3.3.13 of Reference G. 1, the uncertainties listed above are considered 2 sigma (95% probability/95% confidence) unless otherwise specified.

Calculation No.97-023 1 Revision 002-C Page 23 of 72 7.1.2 Total Loop Error Equation Summary (TLE)

The general equation for total instrument loop error is found in Ref. G. 1. This methodology uses the square root of the sunl of the squares (SRSS) method to combine the applicable random and independent errors, and algebraic addition of non-random or bias errors (of like sign).

7.1.2.1 Steam Driven Pump Switchover/Trip Total Loop Error (TLESWTCHO~E~RIP-STEAM)

Per Figure 6.2-1, the total loop error for the steam driven pump low-low suction pressure switchoverltrip function contains the uncertainties for the Sensor, Current-to-Voltage Converter, and Bistable:

sa2+ 1va2+ Ba2+ Sd2+ I V ~ '+ Bd' + Sm2+ 1vm2+ Bm2+ Sv2 TLE,wTc,,,,-sT,, = rt + 1vv2+ Bv2+ Sp2+ 1vp2+ Bp2+ st2+ 1vt2+ 13t2+ sh2+ IVh2 rt Bias

+ Bh2+ Sr2+ IVr2+ Br2+ Ss2+ IVS' + BS' + sspe% -tope2 7.1.2.2 Steam Driven Pump-AlarmTotral Loop Error (TLEALARM-STEAM)

Per Figure 6.2-1, the total loop error for the steam driven pump low suction pressure alarm function contains the uncertainties for the Sensor, Current-to-Voltage Converter, Voltage-to-Current Converter, and Bistable:

=. rt

+ Win2 + ~m~ + 8v2 + IVv2 + VIv2 + B V ~+ sP2+ 1vP2+ VIP2 + BP2 TLEAURM-STEAM rt Bias

\ + s t 2 +IVt2 +VIt2 + B t 2 + s h 2 +IVh2 +VIh2 + B h 2 + s r 2 +IVr2 . ,

1+ VIr2 + Br2 + s s 2 + IVs2 + v1s2 + Bs2 + Sspe2 + Sope2

Calculation No.97-023 1 Revision 002-C Page 24 of 72 7.2 As-Found Tolerance Equation Summary As-Found Tolerances are calculated independently for each of the loop components. The equations shown are adapted f?kom Section 3.3.8.6 of Reference G.l for use in this calculation.

7.2.1 Sensor As-Found Tolerance (SAF)

The acceptable As-Found Tolerance for the Sensor (SAF) is calculated using the following equation:

SAF = i ,,/sv2 + ~ d +sm2 where:

Sv = Sensor Setting Tolerance Sd = Sensor Drift Sm = Sensor M&TE error 7.2.2 Current-to-Voltage As-Found Tolerance-(WAF)

The acceptable As-Found Tolerance for the Current-to-Voltage Converter (IVAF) is calculated using the following equation:

where:

IVV= Current-to-Voltage Converter Setting Tolerance IVd = Current-to-Voltage Converter Drift IVm = Current-to-Voltage Converter M&TE error 7.2.3 Voltage-to-Current As-Found Tolerance (VIAF)

The acceptable As-Found Tolerance for the Voltage-to-Current Converter (VIAF) is calculated using the following equation:

where:

VIV= Voltage-to-Current Converter Setting Tolerance VId = Voltage-to-Current Converter Drift VIm = Voltage-to-Current Converter M&TE error

Calculation No.97-023 1 Revision 002-C Page 25 of 72 7.2.4 Bistable As-Found Tolerance (BAF)

The acceptable As-Found Tolerance for the Bistable (BAF) is calculated using the following equation:

where:

Bv = Bistable Setting Tolerance Bd = Bistable Drift Bm= Bistable M&TE error 7.3 As-Left Tolerance Equation Summary As-Left Tolerances are calculated independently for each of the loop components. The equations shown are adapted fi-ornSection 3~3.8.6of-Keference G.l for use in this calculation.

7.3.1 Sensor As-Lef&Tolerance(SAL)

The As-Left Tolerance for the Sensor (SAL) is equal to its setting tolerance:

SAL=+Sv Where:

Sv = Sensor Setting Tolerance 7.3.2 Current-to-Voltage Converter As-Left Tolerance (IVAL)

The As-Left Tolerance for the Current-to-Voltage Converter (IVAL) is equal to its setting tolerance:

IVAL = f IVv Where:

IVV= Current-to-Voltage Converter Setting Tolerance

Calculation No. 97-0231 Revision 002-C Page 26 of 72 7.3.3 Voltage-to-Current Converter As-Left Tolerance (VIAL)

The As-Left Tolerance for the Voltage-to-Current Converter (VIAL) is equal to its setting tolerance:

VIAL=+VIv Where:

VIV= Voltage-to-Current Converter Setting Tolerance 7.3.4 Bistable As-Left Tolerance (BAL)

The As-Left Tolerance for the Bistable (BAL) is equal to its setting tolerance:

BAL=+Bv Where:

Bv = Bistable Setting Tolerance 7.4 Calculated Setpoint (SP)-Equation Summary Per Section 3.3.8.5 of Reference G.l, for a process increasing toward the analytical limit, the calculated Setpoint is as follows:

For a process decreasing from normal operation toward the analytical limit, the calculated Limiting Trip Setpoint is determined as follows:

Using the setpoint acceptance criteria prescribed in Section 2.0 for a decreasing setpoint.

LTSP 2 SP The FTSP including the required margin to protect the LTSP is determined as follows:

Margin = LTSP - FTSP (Eq. 7.4-3)

Calculation No. 97-0231 Revision 002-C Page 27 of 72 8.0 BODY OF CALCULATION 8.1 Device Uncertainty Analysis This section will determine all applicable uncertainties for the devices that comprise the AF Pump Suction Pressure Alarm/ SwitchoverITrip functions shown in Figures 6.2-1 and 6.2-2.

Per References P.l through P.4, all components in the loop are separately calibrated.

8.1.1 Sensor Accuracy (Sa)

Per Reference V.7, the reference accuracy of the transmitter is 5 0.075 %

calibrated span from 1:1 to 10:1 Range Down Factor. This includes combined effects of terminal-based linearity, hysteresis and repeatability.

Sa = f0.075 % span 8.1.2 Sensor Drift (Sd)

Per Reference V.7, the drift value for the transmitters is rt 0.2 % URL for 30 months. Per References P. 1 and P.2 the transmitters are calibrated every 18 months (or 22.5 months based on 25% extension). As such, the vendor specified thirty month drift value bounds the calibration frequency. Per Section 6.4, the calibrated span is 0 - 30 psig and the URL is 36.063 psig. As such, the drift value in terms of span is calculated below.

Sd = (5 0.20 %

• URL) / span Sd =(& 0.20%

• 36.063 psig) 130 psig Sd = Lt 0.240 % span 8.1.3 Sensor M&TE (Sm)

Per References P.l and P.2, the transmitters are calibrated with the "Fluke Model 45, HP 34401A, or equivalent multimeter approved for current use on a 4-20 mAdc per ICI 12, Selection of M&TE for Field Calibrations." References P.l and P.2 do not provide a required tolerance for a pressure tester with a range of 0

- 30 psig. Therefore, the ICI 12 Microsoft Access Data Base has been reviewed for an appropriate device per the requirements of References P.7 and G. 1.

M&TE uncertainties are calculated separately for the multimeter and pressure tester, and combined to find the total M&TE uncertainty associated with the calibration of the pressure transmitters.

Per References P.l and P.2, either the Fluke Model 45, HP 34401A or an approved equivalent multimeter shall be used for calibration. Therefore, the uncertainties calculated for the Fluke Model 45 and HP 34401A will envelope

Calculation No.97-023 1 Revision 002-C Page 28 of 72 the uncertainties of any other multimeter permitted for use under References P.l and P.2. Per ICI 12 ("Selection of M&TE for Field Calibrationsm-Ref. P.7).

There are 2 devices suited for use as a pressure tester with a range comparable to the instrument tested.

Per P.7 the accuracy of the Aschcroft and McDaniels gauges are k 0.25 % Full Scale and k 0.5 % Full Scale, respectively. Per G.11, the least significant digit of ICTI-621 is 3 digits to the right of the decimal. Therefore, the readability is +

0.001 psig. Per G.1 Section 3.3.4.4, for reading error associated with M&TE that employs an analog (graduated) scale, the associated uncertainty in this reading is

& % of the smallest division. Per G.1 Section 3.3.5.3 if divisions are more closely spaced, ic 50% of the difference between divisions may be more appropriate. Per G. 11, the minor division of the McDaniels gauge is 0.1 psig and should be considered closely spaced. Due to the close spacing, & 50% of the difference between divisions will be taken the readability.

Per G. 1 Section 3.3.4.4 of Reference G.l based on the practices observed by the station, Calibration Standard Error (RAstd) is considered negligible.

Each of the equipment device uncertainties is calculated below:

Multimeter (Output M&TE):

For the Flulte 45 multimeter (medium resolution, 30 mA ranve, 5 digit display)

(Ref V8):

Wmte = uncertainty

• maximum reading Mmtc = + 0.05 % reading

• 20 rnAdc + 3 DGTS ICel-mte = k 0.05 % reading

• 20 mAdc + 3*(1 a)

Urn,, = k 0.05 % reading :': 20 mAdc + 0.003 mnA ICtl-mte =rt0.013 mAdc The readability for digital indicators is defined as the least significant digit, per Ref G. 1:

From Section 3.3.4.4 of Reference G.1, M&TE uncertainty is calculated using the following equation:

A, Calculation No.97-023 1

. \

s a ~ r z yb,.~ntidy~~~ Revision 002-C i /

i

,F' Page 29 of 72 HP 34401A multirneter (6.5 digit display, 100 mAdc range) (Ref. V.6)

M m t e +

= f (0.050 % reading 0.005 % range)

RJLtc +

= f [0.050 % (20 mAdc) 0.005 % (100 mAdc)]

R.Amtc = f 0.015 mAdc W n t c = f 0.0001 mAdc From Section 3.3.4.4 of Reference G. 1, M&TE uncertainty is calculated using the following equation:

The worst case and bounding output M&TE error is Smm = k0.015 mAdc.

Converting to % span:

Sm HP = f 0.015 mAdc * (100 % span / 16 mAdc)

Sm HP =k 0.094 % span Pressure Testers (Input M&TE):

For the Ashcroft 452074SD02L 30 psig digital gauge RAmtc = uncertainty

• instrument range M m t c = f 0.25 % full scale

• 30 psig M m t e = f 0.075 psig m m t e = f 0.001 psig From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

SmPT-AshcroR = f J0.075~ + o2 + 0.001~ = f 0.075 psig For the McDaniels 30 psig gauge M m t c = uncertainty

• instnunent range M m t e = f 0.5 % full scale

• 30 psig

Calculation No.97-023 1 Revision 002-C Page 30 of 72 RArntC = % 0.15 psig m m t c = rt 50% of the difference between divisions mm,c = +0.5*0.1 psig mmtc = IfI 0.05 psig From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

Sm PT-McDaniels =k 6 0 . 1 5 ~+02 +0.05' = f 0.158 psig The worst case and bounding input M&TE error is SmM,D,,iels= f 0.158 psig.

Converting to % span:

Sm PT = k 0.158 psig * (100 % span / 30 psig)

Sm PT = + 0.527 % span The total M&TE uncertainty for the calibration of the pressure transmitter is calculated using the multiple M&TE equation given in Section 3.3.4.4 of Reference G. 1:

Sm = f 0.535 % span 8.1.4 Sensor Setting Tolerance (Sv)

Per Assumption 5.1.4, pressure transmitters 1PT-4044A and 2PT-4044A have a

+

setting tolerance of 0.04 mAdc.

For 1(2)PT-4044A:

Sv,., = rt 0.04 mAdc * (100 % span 1 16 mAdc)

SvSte,, = f0.25 % span

Calculation No.97-023 1 Revision 002-C Page 3 1 of 72 8.1.5 Sensor Power Supply Effect (Sp)

Per Reference V.2, the Current-to-Voltage Converters provide +24 Vdc to the transmitters via an internal dc-to-dc converter, which is supplied from the Spec 200 system 30 Vdc nest field bus. The rack power supply is a regulated rt 15 Vdc f 5% power supply with an output voltage variation of:

(f 5%

• 30 Vdc/ 100 %) = f 1.5 Vdc Per Reference V.7, the transmitter has a power supply effect of less than rt 0.005% span per voltage change.

Sp = rt (0.005 % span / voltage change)

• 1.5 Vdc Sp = f 0.0075 % span 8.1.6 Sensor Temperature Effect (St)

Per Reference V.7, the transmitter has a temperature effect o f f (0.0125 % URL

+ 0.0625 % span) from 1:1 to 5: 1 per 50 OF (28 "C) ambient temperature change.

Per Section 6.5.1, the temperature range in the Auxiliary Feedwater Pump Cubicles (Control Building) is 60 OF to 120 OF. Therefore, the maximum temperature change for accident conditions is 60 OF.

St =f [0.0125% * (36.063 psig / 30 psig) + (0.0625 % )] * (60 OF / 100 OF)

St = rt 0.047 % span 8.1.7 Sensor Humidity Effect (Sh)

Per Ref. V.7, the Rosemount 3051N will function correctly under 0 % - 100%

relative humidity.

Per Section 6.5.1, the humidity in the Auxiliary Feedwater Pump Cubicles (Control Building) is 95%. This humidity is bounded by the humidity range specified by the vendor. Therefore, Sh = f 0.0  % span 8.1.8 Sensor Radiation Effect (Sr)

Per Section 6.5.1, the AF Pump Cubicle Area is outside the Radiologically Controlled Area (RCA), and is not subject to high radiation levels during accident conditions. Further, per Section 3.3.3.21 of Ref. G.l, radiation errors are typically small when compared with other instrument uncertainties, and are adjusted out at every instrument calibration. Therefore, Sr = f 0.0 % span

Calculation No.97-023 1 Revision 002-C Page 32 of 72 8.1.9 Sensor Seismic Effect (Ss)

Per Section 7.1.C, seismic uncertainties must be considered in this calculation.

Reference V.7 indicates a seismic effect for the transmitter of 4 0.75 % URL during and 4 0.25 % of the span after seismic event. Per Section 6.4, the transmitter URL is 36.063 psig and the calibrated span is 30 psig. The uncertainty is calculated using the value during a seismic event to achieve a conservative result. In addition, the sensor would be recalibrated subsequent to a seismic event, so the during- and after-event values not considered random with respect to each other.

Ss = + (0.75 % 36.063 psig) * (100 % span / 30 psig)

F Ss = + 0.902 % span 8.1.10 Sensor Static Pressure Effect (Sspe)

Per Reference G.1, Section 3.3.4.1 1, static pressure effects due to change in process pressure only apply to differential pressure instruments in direct contact with the process. Therefore, Sspe = + 0.0 % span 8.1.11 Sensor Overpressure Effect (Sope)

The normal supply to the AF pumps is the CSTs which are vented tanks (Reference D.l). If the supply is switched to Service Water (due to a low suction pressure event), the suction pressure would be 120 psig (Reference C.3). Per Reference V.7, the overpressure limit is 3626 psig and when exceeded will cause a zero shift of rt 0.25 % URL for the Rosemount 305 1N range code 3 transmitters. Since the pressure of the normal and alternate AF pump water sources is well below the maximum overpressure rating, the transmitter overpressure effect is considered to be negligible.

Sope = It: 0.0 % span 8.1.12 Current-to-Voltage Converter Accuracy (TVa)

Per Reference V.2, the Current-to-Voltage Converter Accuracy is + 0.25 % of the output span.

IVa = + 0.25 % span

Calculation No.97-023 1 Revision 002-C Page 33 of 72 8.1.13 Current-to-Voltage Converter Drift (IVd)

Per Reference V.2, the vendor does not specify a drift value for the IV converter.

Per Section 3.3.3.15 of Ref. G. 1, in the absence of an appropriate drift analysis and when drift is unspecified by the vendor, the instrument's accuracy is used as the instrument drift over the entire calibration period.

IVd = 5 0.25 % span 8.1.14 Current-to-Voltage Converter M&TE Per References P.3 through P.4, the Current-to-Voltage Converter is calibrated with a multimeter capable of measuring 0-10 Vdc (output M&TE) and 4-20 mAdc (input M&TE). Therefore, M&TE uncertainties are calculated separately for each of the mnultimeters, and combined to find the total M&TE uncertainty associated with the calibration of the IV converter.

Per G.l Section 3.3.4.4 of Reference G.l based on the practices observed by the station, Calibration Standard Error (RAstd) is considered negligible.

Per ICI 12 ("Selection of M&TE for Field Calibrationsw-Ref. P.7), there are 2 devices that meet the required criteria for the output M&TE, and 2 devices that meet the required criteria for the input M&TE. Each of the equipment device uncertainties is calculated below:

Multimeter (Output M&TE):

HP 34401A.multimeter(6.5 digit display, 10.0 Vdc range) (Ref. V.61 R.&tC +

= f (0.0035 % reading 0.0005 % range)

RAmt, +

= (0.0035 % (10 Vdc) + 0.0005 % (10 Vdc)]

R&t, =f 0.0004 Vdc RDmte = f 0.00001 Vdc From Section 3.3.4.4 of Reference G.1, M&TE uncertainty is calculated using the following equation:

IVm~p

= f d0.0004~ + o2 + 0.000012 =i0.0004 Vdc

Calculation No. 97-0231 Revision 002-C Page 34 of 72 Fluke 45 multimeter (slow resolution, 5 digit display, 10 Vdc range) (Ref V.8):

RAmtc = f 0.025% reading + 6*(100 pVdc) u rn ,c = f 0.025% reading + 0.0006 Vdc R.&t~t~ = f 0.025% reading

• 10 Vdc + 0.0006 Vdc Wmtc = f 0.003 1 Vdc The readability for digital indicators is defined as the least significant digit, per Ref G. 1:

RD~ntc = If: 0.001 Vdc From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

The worst case and bounding output M&TE error is IVrnd5 = f0.0033 Vdc.

Converting to % span:

Ivm 45 = rt 0.0033 Vdc :k (100 % span 1 10 Vdc)

IVm 45 =f 0.033 % span Multimeter (Input M&TE):

For the Fluke 45 multimeter (medium resolution, 30 mnA range, 5 dipit display)

(Ref V. 8):

Rfbntc *

= uncertainty maximum reading RAmt, *

= rt 0.05 % reading 20 mAdc + 3 DGTS RAmtc * +

= rt 0.05 % reading 20 mAdc 3*(1 pA) u n t c *

= f 0.05 % reading 20 lnAdc + 0.003 mA RAntc = + 0.013 mAdc RDmte = rt 0.001 mAdc From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

Calculation No.97-023 1 Revision 002-C Page 35 of 72 HP 34401A multirneter (6.5 digit dis~lay,100 mAdc range) (Ref. V.6)

M m t c = i (0.050 % reading + 0.005 % range)

M m t e = + [0.050 % (20 inAdc) + 0.005 % (100 mAdc)]

RLntc =It: 0.015 mAdc RDmte = If: 0.0001 mAdc From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

The worst case and bounding output M&TE error is IVmm = k0.015 mAdc.

Converting to % span:

IVm = Ifl0.094 % span The total M&TE uncertainty for the calibration of the current-to-voltage converter is calculated using the multiple M&TE equation given in Section 3.3.4.4 of Reference G. 1:

IVm =f 0.100 % span

Calculation No.97-023 1 Revision 002-C Page 36 of 72 8.1.15 Current-to-Voltage Converter Setting Tolerance (IVv)

Per Assumption 5.1.4 and References P.3 through P.4, the Current-to-Voltage

+

Converter Setting Tolerance is 0.05 Vdc.

IVV = calibration tolerance "'1 00% span / calibrated span)

IVV = + 0.05 Vdc * (100% span 110 Vdc)

IVv = rt 0.5 % span 8.1.16 Current-to-Voltage Converter Power Supply Effect (IVp)

Per Reference V.2, the Current-to-Voltage Converter has a supply voltage effect

+

of 0.2 % of span for a + 5 % change in input voltage. As noted in Section 8.1.5, a + 5% Vdc power supply change is considered. Therefore, IVp = f 0.2 % span 8.1.17 Current-to-Voltage Converter Temperature Effect (IVt)

Per Reference V.2, the Current-to-Voltage Converter Temperature Effect is k0.5 % of output span maximum for a 50 OF change within normal operating limits of 40 OF to 120 O F .

Per Section 6.5.1, the Current-to-Voltage converters employed in the Steam Driven AF Pump Suction Pressure Switchover/Trip/Alarmloops are located in the AF Pump Cubicles (Control Building).

Steam Driven Loop IV Converters (LVtst,,,).

Per Section 6.5.1, the temperature range in the Auxiliary Feedwater Pump Cubicles (Control Building) is 60 OF to 120 OF. Therefore, the maximum temperature change for accident conditions is 60 OF.

Converting to % span:

I V t = If: 0.06 Vdc * (100 % span / 10 Vdc)

IVtSt,,, = rt 0.6 % span 8.1.18 Current-to-Voltage Converter Humidity Effect (IVh)

Per Section 6.5.1, the Current-to-Voltage converters employed in the Steam Driven AF Pump Suction Pressure Switchover/Trip/Alarmloops are located in the AF Pump Cubicles (Control Building).

Calculation No.97-023 1 Revision 002-C Page 37 of 72 Per Section 3.3.3.20 of Ref. G.1, humidity effects should be incorporated when provided by the vendor. Otherwise, changes in humidity are assumed to have a negligible effect on the instrument uncertainty.

Per Ref. V.2, the vendor does not specifL a humidity effect for the IV converters.

Therefore, IVh =f 0.0 % span 8.1.19 Current-to-Voltage Converter Radiation Effect (IVr)

Per Section 6.5.1, the Current-to-Voltage converters employed in the Steam Driven AF Pump Suction Pressure Switchover/Trip/Alann loops are located in the AF Pump Cubicles (Control Building).

Steam Driven Loou IV Converters (IVrstea,,J Per Section 6.5.1, the radiation level in the Auxiliary Feedwater Pump Cubicles (Control Building) 400 RADs (40 year dose).

Per Section 6.5.1, the AF Pump Cubicle Area is outside the Radiologically Controlled Area (RCA), and-isnot subject to high radiation levels during accident conditions. Further, per Section 3.3.3.21 of Ref. G. 1, radiation errors are typically small when compared with other instrument uncertainties, and are adjusted out at every instrument calibration. Therefore, IVrSt,,, = f 0.0 % span 8.1.20 Current-to-Voltage Converter Seismic Effect (IVs)

Per Section 3.3.4.10 of Reference G.1, the effects of seismic or vibration events for non-mechanical instrumentation are considered zero unless vendor or industry experience indicates otherwise.

The vendor does not report a seismic effect for the Current-to-Voltage Converter (Reference V.2). Therefore, IVs = f 0.0 % span 8.1.21 Voltage-to-Current Converter Accuracy (VIa)

+

Per Reference V.3, the Voltage-to-Current Converter Accuracy is 0.5 % of output span.

VIa = f 0.5 % span

Calculation No.97-023 1 Revision 002-C Page 38 of 72 8.1.22 Voltage-to-Current Converter Drift (VId)

Per Reference V.3, the vendor does not specify a drift value for the V/I converter.

Per Section 3.3.3.15 of Ref. G.1, in the absence of an appropriate drift analysis and when drift is unspecified by the vendor, the instrument's accuracy is used as the instrument drift over the entire calibration period.

VId = + 0.5 % span 8.1.23 Voltage-to-Current Converter M&TE (VIm)

Per Reference P.3 - P.4, the Voltage-to-Current Converter is calibrated with a multimeter capable of measuring 4-20 mAdc (output M&TE) and 0-10 Vdc (input M&TE). Therefore, M&TE uncertainties are calculated separately for each of the multimeters, and combined to find the total M&TE uncertainty associated with the calibration of the VI converter.

Per G.l Section 3.3.4.4 of Reference G.l based on the practices observed by the station, Calibration Standard Error (RAstd) is considered negligible.

Per ICI 12 ("Selection of M&TE for Field Calibrationsy'-Ref. P.7), there are 2 devices that meet the required criteria for the output M&TE, and 2 devices that meet the required criteria for the input M&TE. Each of the equipment device uncertainties is calculated below:

Multimeter (Output M&TE):

For the Flulce 45 multimeter (medium resolution, 30 mA range, 5 digit display]

(Ref V.8):

Mmte = uncertainty "' maximum reading Mmtc * +

= Ifl 0.05 % reading 20 mAdc 3 DGTS Rhtc *

= Ifl 0.05 % reading 20 mAdc + 3*(1 pA)

Wmtc = If10.05 % reading

• 20 mAdc + 0.003 mA RAm, = Ifl 0.013 mAdc The readability for digital indicators is defined as the least significant digit, per Ref G. 1:

RDmtc = Ifl 0.001 mAdc From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

Calculation No. 97-0231 Revision 002-C Page 39 of 72 HP 34401A multimeter (6.5 digit display, 100 d d c range) (Ref. V.61 R&,~c = Ifl (0.050 % reading + 0.005 % range)

R&nt~ = Ifl [0.050 % (20 mAdc) + 0.005 % (100 mnAdc)]

Mmte = Ifl 0.015 ~nAdc m n t c = Ifl 0.0001 d d c From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

The worst case and bounding output M&TE error is VImw = 40.015 mAdc.

Converting to % span:

VIm = 4 0.094  % span Multimeter (Input M&TE):

HP 34401A multirneter (6.5 digit display, 10.0 Vdc range) (Ref. V.61 RJhC t = Ifl (0.0035 % reading + 0.0005 % range)

Mmtc = Ifl [0.0035 % (10 Vdc) + 0.0005 % (10 Vdc)]

Mmte = rt 0.0004 Vdc R.Dmtc = IflO.OOOO1 Vdc From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

Calculation No.97-023 1 Revision 002-C Page 40 of 72 Flulce 45 ~nultirneter(slow resolution, 5 digit display, 10 Vdc range) (Ref V.8):

R.&lt~ = + 0.025% reading + 6*(100 fldc)

M m t e = rt 0.025% reading + 0.0006 Vdc mite = + 0.025% reading

• 10 Vdc + 0.0006 Vdc M m t e = k0.003 1 Vdc The readability for digital indicators is defined as the least significant digit, per Ref G. 1:

RDmtc = + 0.001 Vdc From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

The worst case and bounding input M&TE error is VIm45= rt0.0033 Vdc.

Converting to % span:

V1J.n 45 = + 0.0033 Vdc * (100 % span / 10 Vdc)

VIm d5 = TfI 0.033 % span The total M&TE uncertainty for the calibration of the current-to-voltage converter is calculated using the multiple M&TE equation given in Section 3.3.4.4 of Reference G.1:

VIm =+Jo.033~+0.094~

VIm = rt 0.100 % span

Calculation No.97-023 1 Revision 002-C Page 41 of 72 8.1.24 Voltage-to-Current Converter Setting Tolerance (VIv)

Per Assumption 5.1.4 and References P.3 - P.4, the Voltage-to-Current

+

Converter Setting Tolerance is 0.08 mnAdc.

VIV = setting tolerance * (100% span / calibrated span)

VIV = rt 0.08 mA.dc * (100% span 116 mnAdc)

VIV = f 0.5 % span 8.1.25 Voltage-to-Current Converter Power Supply Effect (VIP)

Per Reference V.3, the Voltage-to-Current Converter has a supply voltage effect of rt 0.5 % of output span for a k 5 % change in input voltage. As noted in Section 8.1.5, a k 5% Vdc power supply change is considered. Therefore, VIp = f 0.5 % span 8.1.26 Voltage-to-Current Converter Temperature Effect (VIt)

Per Reference V.3, the Voltage-to-Current Converter Temperature Effect is rt 0.5 % of output span maximum for a 50 OF change within nonnal operating limits of 40 OF to 120 OF.

Per Section 6.5.1, the Voltage-to-Current converters employed in the Steam Driven AF Pump Suction Pressure Switchover/Trip/Alarmloops are located in the AF Pump Cubicles (Control Building).

Per Section 6.5.1, the temperature range in the Auxiliary Feedwater Pump Cubicles (Control Building) is 60 OF to 120 OF. Therefore, the maximum temperature change is 60 OF.

Converting to % span:

VIt = rt 0.096 mAdc * (100 % span / 16 mAdc)

VIt = f 0.6 % span 8.1.27 Voltage-to-Current Converter Humidity Effect (VIh)

Per Section 6.5.1, the Voltage-to-Converter converters employed in the Steam Driven AF Pump Suction Pressure Alarm loop is located in the AF Pump Cubicles (Control Building).

Calculation No.97-023 1 Revision 002-C Page 42 of 72 Per Section 3.3.3.20 of Ref. G.1, humidity effects should be incorporated when provided by the vendor. Otherwise, changes in humidity are assumed to have a negligible effect on the instrument uncertainty.

Per Ref. V.3, the vendor does not specify a humidity effect for the VI converters.

Therefore, VIh =f 0.0 % span 8.1.28 Voltage-to-Current Converter Radiation Effect (VIr)

Per Section 6.5.1, the Voltage-to-Current converters employed in the Steam Driven AF Pump Suction Pressure Alarm loop is located in the AF Pump

.. Cubicles (Control Building).

Per Section 6.5.1, the radiation level in the Auxiliary Feedwater Pump Cubicles (Control Building) is 400 RADs (40 year dose).

Per Section 6.5.1, the AF Pump Cubicle Area is outside-theRadiologically Controlled Area (RCA), and is not subject to high radiation levels during accident conditions. Further, per Section 3.3.3.21 of Ref. G.l, radiation errors are typically small when compared with other instrument uncertainties, and are adjusted out at every instrument calibration. Therefore, VIr =f 0.0 % span 8.1.29 Voltage-to-Current Converter Seismic Effect (VIs)

Per Section 3.3.4.10 of Reference G.l, the effects of seismic or vibration events for non-mechanical instrumentation are considered zero unless vendor or industry experience indicates otherwise.

The vendor does not report a seismic effect for the Voltage-to-Current Converter (Reference V.3). Therefore, VIs = f 0.0 % span 8.1.30 Bistable Accuracy @a)

Per Reference V.4, the Bistable has a rt 0.5 % setpoint repeatability.

Ba =f 0.5 % span

~alculationNo.97-023 1 Revision 002-C Page 43 of 72 8.1.31 Bistable Drift (Bd)

Per Reference V.4, the vendor does not specify a drift value for the bistable unit.

Per Section 3.3.3.15 of Ref. G.l, in the absence of an appropriate drift analysis and when drift is unspecified by the vendor, the instrument's accuracy is used as the instrument drift over the entire calibration period.

Bd = rt 0.5 % span

Calculation No.97-023 1 Revision 002-C Page 44 of 72 8.1.32 Bistable M&TE Effect (Bm)

M&TE Effect for l(2)PC-4044-LL (switchover/trial Per Reference P.3 through P.4, these bistable units are calibrated by applying a voltage signal into the bistable unit, measuring the input signal via a multimeter capable of measuring 0-10 Vdc, and confirming a relay output on the bistable unit (at the desired setpoint).

Per G.l Section 3.3.4.4 of Reference G.l based on the practices observed by the station, Calibration Standard Error (RAstd) is considered negligible.

Per ICI 12 ("Selection of M&TE for Field Calibrationsv-Ref. P.7), there are 2 devices that meet the required criteria for the M&TE. Each of the equipment device uncertainties is calculated below:

HP 34401A multi~neter(6.5 digit display, 10.0 Vdc range) (Ref. V.6)

RAmtc = rt (0.0035 % reading + 0.0005 % range)

Wmtc = k [0.0035 % (10 Vdc) + 0.0005 % (10 Vdc)]

R A ~ ~ c = rt 0.0004 Vdc U s t d =0 mmtc = rt 0.00001 Vdc From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

Fluke 45 multirneter (slow resolution, 5 digit display, 10 Vdc range) (Ref V.8):

RArnte = rt 0.025% reading + 6*(100 pVdc)

RArntc = k 0.025% reading + 0.0006 Vdc RAmtc = rt 0.025% reading

• 10 Vdc + 0.0006 Vdc M m t e = rt 0.003 1 Vdc The readability for digital indicators is defined as the least significant digit, per Ref G. 1:

mmte = rt 0.001 Vdc

Calculation No.97-023 1 Revision 002-C Page 45 of 72 From Section 3.3.4.4 of Reference G.1, M&TE uncertainty is calculated using the following equation:

The worst case and bounding M&TE error is Bm45= f0.0033 Vdc.

Converting to % span:

Bm 45 = rt 0.0033 Vdc * (100 % span / 10 Vdc)

Bm 45 =f 0.033 % span M&TE Effect for l(2)PC-4044-L (alarm1 Per Reference P.3 - P.4, these bistable units are calibrated by injecting a current signal into the bistable unit (over a 500 R resistor connected across the calibration point per Ref. D..3 - D.4), measuring the input signal via a multimeter capable of measuring 4-20 mAdc, and c o d i n g a relay output on the bistable unit (at the desired setpoint). This calculation does not consider any uncertainty value associated with the 500 R resistor because effects are calibrated out during calibration.

Per G. 1 Section 3.3.4.4 of Reference G. 1 based on the practices observed by the station, Calibration Standard En-or (RAstd) is considered negligible.

Per ICI 12 ("Selection of M&TE for Field Calibrations"- Ref. P.7), there are 2 devices that meet the required criteria for the M&TE. Each of the equipment device uncertainties is calculated below:

For the Fluke 45 multimeter (medium resolution, 30 mA range, 5 digit display)

(Ref V. 8):

RArnte = uncertainty

• maximum reading Wmte = If: 0.05 % reading

• 20 mAdc + 3 DGTS Mmte = rt 0.05 % reading

• 20 mAdc + 3*(1 pA)

RAmtc = rt 0.05 % reading

• 20 mAdc + 0.003 mA Wmte = rt 0.013 mAdc The readability for digital indicators is defined as the least significant digit, per Ref G. 1:

RDmte = rt 0.001 mAdc

Calculation No. 97-0231 Revision 002-C Page 46 of 72 From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

Sm MM45 + o2 + 0.0012 = f 0.013 mAdc

= f4 0 . 0 1 3 ~

HF' 34401A multimeter (6.5 dinit dis~lav,100 mAdc range) (Ref. V.6)

R.Arnte = rt (0.050 % reading + 0.005 % range) w m t e = rt [0.050 % (20 mAdc) + 0.005 % (100 mAdc)]

RJhntc = rt 0.015 mAdc mmte = rt 0.0001 mAdc From Section 3.3.4.4 of Reference G.l, M&TE uncertainty is calculated using the following equation:

The worst case and bounding M&TE error Bmm = k0.015 mAdc.

Converting to % span:

Bm IW = f 0.01 5 mAdc * (100 % span 1 16 mAdc)

Bm EIP = k 0.094 % span 8.1.33 Bistable Setting Tolerance (Bv)

Per Assumption 5.1.4 and References P.3 and P.4, bistables 1(2)PC-4044-LL (switchoverltrip) have a setting tolerance of f 0.020 Vdc. Note that this bistable is configured for single setpoint action (switchoverltrip function).

Per Assumption 5.1.4 and References P.3 and P.4, bistables l(2)PC-4044-L (alarm) have a setting tolerance of f 0.03 mAdc (due to a 500 Q resistor connected across the calibration point per Ref. D.3 - D.4). Note that this bistable is configured for single setpoint action (alarm function).

,/" Calculation No.97-023 1 1

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.,,/ Page 47 of 72 Steam Driven Loop Bistable (SwitchoverITrip) Setting Tolerance ( B v ~ ~ ~ ~ ~ - ~ L )

BV~,,,,-LL= t 0.020 Vdc (100 % span / 10 Vdc)

Bvstcam-L~=rt 0.2 % span Steam Driven Loop Bistable (Alarm) Setting Tolerance (Bv,~,:,,.L]

B~~tearn-~ "

= --f 0.03 mAdc (100 % span / 16 d d c )

BvSteam-~= ft 0.1875 % span 8.1.34 Bistable Power Supply Effect (Bp)

Per Reference V.4, the Bistable has a power supply effect o f t 0.25 % for a 5 %

change in supply voltage. As noted in Section 8.1.5, a a 5% Vdc power supply change is considered. Therefore, Bp = rt 0.25 % span 8.1.35 Bistable Temperature Effect (Bt)

Per Reference V.4, the Bistable Unit Temperature Effect is t0.5 % of input span maximum for a 50 OF change within normal operating limits of 40 OF to 120 OF.

Per Section 6.5.1, the bistable unit employed in the Steam Driven AF Pump Suction Pressure Switchover / Trip is located in the AF Pump Cubicles (Control Building). The bistable unit employed in the Steam Driven AF Pump Suction Pressure Alarm is located in the Computer Room.

Per Section 6.5.1, the temperatures in the Auxiliary Feedwater Pump Cubicles (Control Building) are range fiom 60 OF to 120 OF. Therefore, the maximum temperature change is 60 OF.

Btstearn-LL = t(0.5  % :': 10 Vdc) * (60 OF / 50 OF)

Btsteam-LL =t (0.05 Vdc) * (1.2)

Btstearn-LL = rt 0.06 Vdc Converting to % span:

Btstearn-LL = t0.06 Vdc * (100 % span / 10 Vdc)

Btsteam-LL = rt 0.6 % span

Calculation No.97-023 1 Revision 002-C Page 48 of 72 Alarm Bistable Temperature Effect (Btstcam-L).

Per Section 6.5.2, the temperatures in the computer room range from 65 OF to 120 OF (due to a loss of the non-safety related HVAC cooling unit). Therefore, the maximum temperature change is 55 OF.

Btstenrn-L = + (0.5 %

• 16 mnAdc) * (55 OF / 50 OF)

Btstearn-L = + (0.08 mnAdc) * (1.1)

Btstearn-L = + 0.088 mAdc Converting to % span:

Btstcnm-L = 2 0.088 mAdc * (100 % span / 16 mAdc)

Btstenm-L = f 0.55 % span 8.1.36 Bistable Humidity Effect (Bh)

Per Section 6.5.1, the bistable units employed in the Steam Driven AF Pump Suction Pressure Switchover/Trip loop is located in the AF Pump Cubicles (Control Building). Per Section 6.5.2, the bistable units employed in the Steam Driven AF Pump Suction~PressureAlarm loop are located in the Computer Room.

Per Section 3.3.3.20 of Ref. G.1, humidity effects should be incorporated when provided by the vendor. Otherwise, changes in humidity are assumed to have a negligible effect on the instrument uncertainty.

Per Ref. V.4, the vendor does not specify a humidity effect for the bistable units.

Bh = f 0.0 % span 8.1.37 Bistable Radiation Effect (Br)

Per Section 6.5.1, the bistable unit employed in the Steam Driven AF Pump Suction Pressure Switchover/Trip is located in the AF Pump Cubicles (Control Building). The bistable unit employed in the Steam Driven AF Pump Suction Pressure Alarm is located in the Computer Room. Per Sections 6.5.1 and 6.5.2, the AF Pump Cubicles (Control Building) environmental conditions are harsher than in the Computer Room. As such, for simplicity purposes, all Steam Driven AF Pump Suction Bistables are conservatively evaluated under the AF Pump Cubicles (Control Building) environmental conditions.

Steam Driven Loop Bistable Units (Brsteam).

Per Section 6.5.1, the radiation levels in the Auxiliary Feedwater Pump Cubicles (Control Building) is 400 RADs.

Calculation No.97-023 1 Revision 002-C Page 49 of 72 Per Section 6.5.1, the AF Pump Cubicle Area is outside the Radiologically Controlled Area (RCA), and is not subject to high radiation levels during accident conditions. Further, per Section 3.3.3.21 of Ref. G.1, radiation errors are typically small when compared with other instrument uncertainties, and are adjusted out at every instrument calibration. Therefore, BrSt,,, = f 0.0 % span 8.1.38 Bistable Seismic Effect (Bs)

Per Section 3.3.4.10 of Reference G.1, the effects of seismic or vibration events for non-mechanical instrumentation are considered zero unless vendor or industry experience indicates otherwise.

The vendor does not report a seismic effect for the bistable units (Reference V.4).

Bs = rt 0.0 % span 8.2 Process Error (PE)

The normal source of the Auxiliary Feedwater Pumps is the Condensate Storage Tanks.

As pump suction pressure-lowers to a predeteimined value, the pressure instrument loops alarm and switchoverltrip in order to prevent damage to the AF pumps. Since these pressure sensors (transmitters) are located in a location where environmental conditions, such as temperature, may vary, Process Error must be evaluated.

However, Section 6.6 utilized a temperature of 40 OF to determine the minimum pressure at which a switchoverltrip initiation must occur to protect the AF pumps. This temperature is considered conservative because it provides the largest possible density of water in the AF piping, thus providing the highest possible minimum pressure. An increase or decrease in temperature (from 40 OF) will create a lower density of water, causing the transmitter to receive a lower pressure and consequently cause an early switchoverltrip initiation. Therefore, process errors, due to changes in temperature, are accounted for in determining the conservative analytical limit (AL)value.

PE = f 0.0 % span

Calculation No.97-023 1 Revision 002-C Page 50 of 72 8.3 Device Uncertainty Summary 8.3.1 Sensor Uncertainties Parameter Uncertainty (% span) I Ref. Section Sensor Accuracy (Sa) rt 0.075 % 8.1.1 Sensor Drift (Sd) t 0.240% 8.1.2 Sensor M&TE (Sm) t 0.535 % 8.1.3 Sensor Setting Tolerance (Sv) Irt 0.25 % 8.1.4 Sensor Power Supply Effect (Sp) rt 0.0075 % 8.1.5 Sensor Temperature Effect (St) t 0.047 % 8.1.6 Sensor Humidity Effect (Sh) A 0.0 % 8.1.7 Sensor Radiation Effect (Sr) 3.0.0 % 8.1.8 Sensor Seismic Effect (Ss) 5 0.902 % 8.1.9 Sensor Static Pressure Effect (Sspe) t 0.0 % 8.1.10 Sensor Overpressure Effect (Sope) A 0.0 % 8.1.11 8.3.2 Current-to-Voltage Converter Uncertainties Parameter I Uncertainty (% span) 1 Ref. Section Current-to-Voltage Converter t- 0.25 % 8.1.12 Accuracy (IVa)

Current-to-Voltage Converter Drift (IVd)

+ 0.25 % 8.1.13 Current-to-Voltage Converter 8.1.14 t- 0.100 %

M&TE (IVm)

Current-to-Voltage Converter Setting Tolerance (IVv)

+ 0.5 % 8.1.15 Current-to-Voltage Converter t 0.2 % 8.1.16 Power Supply Effect (IVp)

Current-to-Voltage Converter Temperature Effect (IVt)

+ 0.6% 8.1.17 Current-to-Voltage Converter rt 0.0 % 8.1.18 Humidity Effect (IVh)

Current-to-Voltage Converter

-t 0.0 % 8.1.19 Radiation Effect (IVr)

Current-to-Voltage Converter 8.1.20 rt 0.0 %

Seismic Effect (IVs)

,d' Calculation No. 97-0231 i'  :

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/ ' Page 5 1 of 72 8.3.3 Voltage-to-Current Converter Uncertainties Parameter Uncertainty (% span) Ref. Section Voltage-to-Current Converter Accuracy (VIa)

+ 0.5 % 8.1.21 Voltage-to-Current Converter If1 0.5 % 8.1.22 Drift (VId)

Voltage-to-Current Converter M&TE (VIrn) t 0.100 % 1 8.1.23 Voltage-to-Current Converter f 0.5 % 8.1.24 Setting Tolerance (VIv)

Voltage-to-Current Converter If: 0.5 % 8.1.25 Power Supply Effect (VIP)

Voltage-to-Current Converter

=t 0.6% 8.1.26 Temperature Effect (VIt)

Voltage-to-Current Converter Humidity Effect (VIh)

+ 0.0 % 8.1.27 Voltage-to-Current Converter Radiation Effect (VIr)

+ 0.0 % 8.1.28 Voltage-to-Current Converter

- Seismic Effect (VIs)

+ 0.0 % 8.1.29 8.3.4 Bistable Uncertainties Parameter / Uncertainty (% span) Ref. Section Bistable Accuracy (Ba) + 0.5 % 8.1.30 Bistable Drift (Bd) + 0.5 % 8.1.31

= =t 0.033 %

Bistable M&TE (Em) 8.1.32 B v ~= f~0.2~% ~ ~ - ~ ~

Bistable Setting Tolerance (Bv) 8.1.33 B v ~= ~ 0.1875+ ~ ~ %~ - ~

Bistable Power Supply Effect (Bp) + 0.25 % 8.1.34 Btstcam-~~ +

= 0.6 %

Bistable Temperature Effect (Bt) 8.1.35 Btsteam-L = + 0.55%

Bistable Humidity Effect (Bh) + 0.0 % 8.1.36 Bistable Radiation Effect (Br) + 0.0 % 8.1.37 Bistable Seismic Effect (Bs) + 0.0 % 8.1.38

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Page 52 of 72 8.3.5 Process Considerations and Bias Terms 3

Parameter Uncertainty (% span) Ref. Section Process Error (PE) _+ 0.0 % 8.2 Bias Terms (Bias) f 0.0 % 8.1.1 - 8.1.38

Calculation No. 97-0231 Revision 002-C Page 53 of 72 8.4 Total Loop Error Per Section 7.1.2, the Total Loop Error is determined as follows:

8.4.1 Steam Driven Pump Switchover/Trip Total Loop Error (TLESWITCHOVERITRIP-STEAM)

Per Section 7.1.2.1, the AFP Low Low Suction Pressure SwitchoverITrip Function for the steam driven pumps (1P-29 and 2P-29) contains uncertainties horn the Sensor, Current-to-Voltage Converter and Bistable.

The TLE Equation from Section 7.1.2.1 is adapted for the specific instrument uncertainties and shown below:

Isa2+ 1va2+ ~ + sd2 a +~1vd2+ ~ d +' Sm2+ 1Vm2+ Bm,, 2 + Sv,,, 2

= f + 1vv2+ B ~ + ~IV~,,,,,~ + Btsleam-L:+ sh2 fBias

~ +~I V~~ '+ ~Bp2-+ St2 v ~ + sp2 2

TLESwTCI-IOVERITRIPRIPSTEAM

+ 1Vh2+ ~h~ + Sr2+ 1vr2+ ~r~ + ss2+ 1vs2+ B S +~Sspe2+ Sope2 Substituting hom the uncertainty tables in Sections 8.3.1, 8.3.2, 8.3.4 and 8.3.5, the Allowances are calculated-as-follows:

TLE SWTCHOVER/TRIP-STEAM = Ifi 1.725 % span * (30 psigI100 % span)

TLE SWTCHOVEWTRIP-STEAM = + 0.518 psig

Calculation No. 97-0231 Revision 002-C Page 54 of 72 8.4.2 Steam Driven Pump Alarm Total Loop Error (TLEALARM-STEAM)

Per Section 7.1.2.2, the AFP Low Suction Pressure Alarm Function for the steam driven pumps (1P-29 and 2P-29) contains uncertainties from the Sensor, Current-to-Voltage Converter, Voltage-to-Current Converter and the Bistable.

The TLE Equation from Section 7.1.2.2 is adapted for the specific instrument uncertainties and shown below:

+ VIm2 + ~ m , , +, Sv

~ ,,,,, + IVV2 + VIV2 + Bv,,,,,. i2 + Sp2 + IVp2 + VIp2

+Bias T L ~ A ~ - , =~5- 2 2 2

\ + Bp + St + I V ~ m2 + VIt + Bt s,ea .ca,- + s h 2 + 1vh2 + VIh2 + Bh2 Substituting from the uncertainty tables in Sections 8.3.1 - 8.3.5, the Allowances are calculated as follows:

TLE ALARM-STEAM = f 2.072 % span "" (30 psigI100 % span)

TLE ALARMSTEAM =f 0.622 psig

Calculation No.97-023 1 Revision 002-c Page 55 of 72 8.5 Acceptable As-Found and As-Left Calibration Tolerances 8.5.1 Acceptable As-Found Calibration Tolerances Per Section 3.3.8.6 of Reference G.l, the As-Found Tolerances are determined using the equations shown in Section 7.2 of this calculation.

Reference P.l through P.4 shows a separate calibration for the Sensor, Current-to-Voltage Converter, Voltage-to-Current Converter, and Bistable. Therefore, the As-Found Tolerance for each device is calculated independently.

8.5.1.1 Sensor As-Found Tolerance (SAF)

Steam Driven Pump Narrow-Range Suction Pressure Transmitter AFT (sAFst"a"&l The equation ikom Section 7.2.1 is adapted for the specific instrument uncertainties and shown below:

where:

Svstmm = 2 0.25 % span Section 8.1.4 Sd = rt 0.240 % span Section 8.1.2 Sm = i 0.535 % span Section 8.1.3 SAFsteam = i 0.6374 % span Converting from % span to mA:

SAF~team = i 0 . 6 3 7 4 % span* (16rnAI 100 %span)

The resulting As-Found Tolerance is rounded to the precision of the associated calibration procedure (Ref. P.l - P.2).

8.5.1.2 Current-to-Voltage Converter As-Found Tolerance (IVAF)

The equation from Section 7.2.2 is adapted for the specific instrument uncertainties and shown below:

Calculation No.97-023 1 Revision 002-C Page 56 of 72 where:

IVv = rt 0.5 % span Section 8.1.15 IVd = rt 0.25 % span Section 8.1.13 IVm = rt 0.100 % span Section 8.1.14 IVAF = rt 60.5' + 0.25' + 0.100' IVAF = rt 0.5679 % span Converting from % span to Vdc:

WAF = rt 0.5679 % span * (10 Vdc / 100 % span)

IVAF = rfi 0.057 Vdc The resulting As-Found Tolerance is rounded to the precision of the associated calibration procedure (Ref. P.3 - P.4).

8.5.1.3 Voltage-to-Current Converter As-Found Tolerance (VLAF)

The equation from Section 7.2.3 is adapted for the specific instrument uncertainties and shown below:

where:

VIv = rt0.5 % span Section 8.1.24 VId = rt 0.5 % span Section 8.1.22 VIm = It 0.100 % span Section 8.1.23 VIAF = rt 60.5' + 0.5' + 0.100' VIAF = rt 0.7141 % span Converting from % span to mA:

VIAF = f 0.11 mA The resulting As-Found Tolerance is rounded to the precision of the associated calibration procedure (Ref. P.3 - P.4).

Calculation No. 97-0231 Revision 002-C Page 57 of 72 8.5.1.4 Bistable As-Found Tolerance (BAF)

Steam Driven Pump Suction Pressure SwitchoverITrio Bistable AFT PAFstcam-LLJ The equation fiom Section 7.2.4 is adapted for the specific instrument uncertainties and shown below:

2 2 B m ~ t e a m - ~=~f ~ +

B v S ~ ~ ~ ~ -~L d L +' Bm45 where:

BvsteamcL = f 0.2 % span Section 8.1.33 Bd = f 0.5 % span Section 8.1.31 Bm45 = f 0.033 % span Section 8.1.32 BAFSleam-LL = f 40.2' + O.S2 + 0.033' BAFSteam-LL = f 0.5395 % span Converting fiom % span to Vdc:

BAFSteam-LL = f 0.5395 % span * (10 Vdc 1 100 % span)

B A F s ~=~rt 0.054~ ~ -Vde~ ~

The resulting As-Found Tolerance is rounded to the precision of the associated calibration procedure (Ref. P.3 - P.4).

Steam Driven Pump Suction Pressure Alarm Bistable AFT PAFsteam-LZ The equation fiom Section 7.2.4 is adapted for the specific instrument uncertainties and shown below:

where:

Bvstcamc = f 0.1875 % span Section 8.1.33 Bd = f 0.5  % span Section 8.1.31 B~HP = f 0.094 % span Section 8.1.32 BAFsteam-L= f 0.5422 % span

Calculation No.97-023 1 Revision 002-C Page 58 of 72 Converting from % span to mAdc:

BAFs,,,,.L = f 0.5422 % span " (16 ~nAdc/ 100 % span)

The resulting As-Found Tolerance is rounded to the precision of the associated calibration procedure (Ref. P.3 - P.4).

8.5.2 Acceptable As-Left Calibration Tolerances Per Section 3.3.8.6 of Reference G.l, the As-Left Tolerance is determined using the equations shown in Section 7.3 of this calculation.

Reference P.l through P.4 shows a separate calibration for the Sensor, Current-to-Voltage Converter, Voltage-to-Current Converter and Bistable. Therefore, the As-Left Tolerance for each device is calculated independently.

8.5.2.1 Sensor As-Left Tolerance (SAL)

Steam Driven Pump Suction Pressure Transmitter ALT (SALsteam)

Using the equation from Section 7.3.1 :

Section 8.1.4 Converting from % span to mAdc:

SALst,,, = rt 0.25 % span * (16 mAdc / 100 % span)

SALst,,, = f 0.04 mAdc 8.5.2.2 Current-to-Voltage Converter As-Left Tolerance (IVAL)

Using the equation from Section 7.3.2:

IVAL = rt IVv IVAL=rtO.5% span Section 8.1.15 Converting from % span to Vdc:

rVAL = rt 0.5 % span * (10 Vdc / 100 % span)

IVAL = f 0.050 Vdc

Calculation No.97-023 1 Revision 002-C Page 59 of 72 8.5.2.3 Voltage-to-Current Converter As-Left Tolerance (VIAL)

Using the equation from Section 7.3.3:

VIAL = rt 0.5% span Section 8.1.24 Converting from % span to mAdc:

VIAL = rt 0.5 % span * (16 mAdc / 100 % span)

VIAL = f 0.08 mAdc 8.5.2.4 Bistable As-Left Tolerance P A L )

Steam Driven Pump Suction Pressure Switchover/Trip Bistable ALT (BALsteam-~~]

Using the equation from Section 7.3.4:

B m ~ t e a r n -=

~2~ B~~tearn-LL BALStearn-LL = rt 0.2 % span Section 8.1.33 Converting from % span to Vdc:

BALStcarn-LL = rt 0.2 % span * (10 Vdc / 100 % span)

Steam Driven Pump Suction Pressure Alarm Bistable ALT

/BALste,m-~)

Using the equation from Section 7.3.4:

BALstearn-~- rt Bvsteam-~

= rt 0.1875 % span Section 8.1.33 Converting from % span to mAdc:

BALstea,-L = rt 0.1875 % span * (16 mAdc / 100 % span)

BALste,m-L = fi 0.03 mAdc

Calculation No.97-023 1 Revision 002-C Page 60 of 72 8.6 Setpoint Evaluation Per Section 7.4, for a process decreasing from normal operation toward the analytical limit, the calculated limiting trip setpoint is determined as follows:

Per Section 7.4, the LTSP is used to determine the margin compared to the existing FTSP as follows:

Margin = LTSP - FTSP These equations are used throughout this section for the evaluation of the TDAFP Suction Pressure Switchover/Trip/AlarmSetpoints.

8.6.1 Steam Driven Pump l(2)P-29 Low-Low Suction Pressure SwitchoverITrip Setpoint Per Section 6.6, the Analytical Limit for the AF Low Pressure Suction StitchoverJTrip is 5.241 psig. Per Section 8.4.1, the random component of the TLE SWTCHOVERITNP-STEAM is 1.725 % span. There is no TLE bias component.

Substituting:

SP sw,Tci.lovEmNP-stcam = 5.241 psig + (1.725 %

• 30 psig + 0)

Using the setpoint acceptance criteria prescribed in Section 2.0 for a decreasing setpoint.

LTSP 2 SP The LTSP is chosen by conservatively rounding the SP to 5.8 psig.

5.8 psig 2 5.759 psig The newly recommended limiting trip setpoint of 5.8 psig is acceptable. Therefore, To protect the LTSP, the FTSP has been selected such that additional margin is provided between LTSP and FTSP. Therefore a value of 6.1 psig has been selected for the FTSP.

Calculation No. 97-0231 Revision 002-C Page 6 1 of 72 Per References P.3 and P.4, the existing l(2)P-29 AF Pump Lo-Lo Suction Pressure Trip Setpoint (FTSP) is 6.6 psig (decreasing). Per Section 2.0, the existing trip setpoint (FTSP) is revised to reflect the lower span of the new switchover/trip loop.

FTSP 2: SP The existing Lo-Lo Suction Pressure Trip Setpoint (FTSP) is not acceptable, and will be revised to 6.1 psig.

Again, using the setpoint acceptance criteria prescribed in Section 2.0, FTSP 2: SP 6.1 psig 2: 5.759 psig Where additional margin is provided to protect the LTSP.

Substituting:

Margin SWITCHOVEWTHP-smm = 1 5.8 psig - 6.1 psig I Moreover, margin is required to be provided for Rack Error (RE?) for the tested portion of the trip channel during normal operation. This includes the Current-to-Voltage Converter and Bistable As-Found Tolerance. Per Section 8.5.1.2 and 8.5.1.4 the uncertainty associated with the Current-to-Voltage Converter and SwitchoverITrip Bistable are used to determine the RE? as follows:

Where:

IVv = i 0.5  % span Section 8.1.15 IVd = i 0.25 % span Section 8.1.13 Nm = i 0.100 % span Section 8.1.14 Bvsteam-LL = ~f:0.2 % span Section 8.1.33 Bd = i 0.5 % span Section 8.1.3 1 Bm45 = f 0.033 % span Section 8.1.32 REas-found= f 0.7833 % span

Calculation No.97-023 1 Revision 002-C Page 62 of 72 Converting from % span to Vdc:

= f0.7833 % span * (10 Vdc / 100 % span)

REas-found REas-found

= f 0.078 Vdc Converting from % span to psig:

= f 0.7833% span * (30 psig / 100 % span)

REas-found REas-found

= 0.235 psig Per Section 8.5.2.2 and 8.6.2.4 the uncertainty associated with the Current-to-Voltage Converter and SwitchoverITrip Bistable are used to determine the RE as follows:

Where:

IVv = f 0.5 % span Section 8.1.15 Bv~tcam-~~ = rt . O l % span Section 8.1.33

= + 0.5385 % span Converting from % span to Vdc:

RE,,I,R +

= 0.5385 % span * (10 Vdc / 100 % span)

= ft 0.054 Vdc Converting from % span to psig:

= f 0.5385% span * (30 psig / 100 % span)

REas-leR= 0.162 psig Margin S W T C H O V E R / T ~ P - S As-Found

~~~ = (LTSP S W T C H O V E R / T R I P - S ~+~ ~m~a s - f o u n d 3

- FTSP SWITCHOVER/TRLP-S~~~~

Substituting:

Margin SWITCHOVEWTRIP-stcnm ~ s - ~ o u n i 0.065

= psig The newly recommended switchover/trip setpoint of 6.1 psig is acceptable.

Therefore,

Calculation No. 97-0231 Revision 002-C Page 63 of 72 Converting from psig to Vdc and conservatively rounding up to the precision of the setpoint:

FTSP S W I T C H O ~ E R ~ I ' R I P -=S2.033

~ ~ ~ -Vdc

~~~

8.6.2 Steam Driven Pump l(2)P-29 Low Suction Pressure.Alarm Setpoint Per Section 6.6, the Analytical Limit for the AF Low Pressure Suction SwitchoverITrip is 5.241 psig. This analytical limit will also be used to evaluate the Lo Suction Pressure Alarm.

Substituting:

SP~~Aw-~tearn = 5.241 psig + (2.072 %

• 30 psig)

SPALARM-S~C~~ = 5.241 psig + 0.622 psig

~PACARM-S~C~= ~ 5.863 psig Per Reference P.3 and P.4, the existing l(2)P-29 AF Pump Lo Suction Pressure Alarm Setpoint (FTSP) is 7.1 psig (decreasing). Per Section 2.0, the existing alarm setpoint (FTSP) is acceptable if it is:

1) Greater than (or equal to) the setpoint calculated in this section (SP)

2) 0.5 psig above the TDAFP Low-Low Suction Pressure SwitchoveriTrip Setpoint.

FTSP 2 SP 7.0 psig is greater than or equal to 5.863 psig.

Although the existing FTSP is greater than (or equal to) the setpoint calculated in this section (SP), it is much greater than 0.5 psig above the TDAFP Low-Low Suction Pressure SwitchoveriTrip Setpoint (based on the switchoveritrip setpoint change prescribed in Section 8.6.1 of this calculation).

As such, the existing alarm setpoint of 7.1 psig will be changed to 6.6 psig to preserve the existing 0.5 psig increment between the switchoveritrip and alarm setpoints and meet the alarm setpoint acceptance criteria.

Therefore, the newly recommended Lo Suction Pressure Alarm setpoint is:

Calculation No. 97-0231 Revision 002-C Page 64 of 72 Converting from psig to 1nAdc and conservatively rounding up to the precision of the setpoint:

FTSPALARM- Stcam-new = 6.6 psig * [(20 d d c - 4 d d c ) / 30 psig)] + 4 d d c

Calculation No.97-023 1 Revision 002-C Page 65 of 72 9.0 RESULTS AND CONCLUSIONS, WITH LIMITATIONS 9.1 Loop Uncertainties The Seismic loop uncertainties (concurrent with accident environments) for Auxiliary Feedwater Punp Low Suction Pressure are su~mna~ized below.

Seismic Conditions 95% / 95% (concurrent with accident environments)

Reference Confidence

% span ~sig TLE SWITCHOVER1 f 1.725 rt 0.518 8.4.1 TRIP-STEAM TLE ALARM-STEAM f 2.072 rt 0.622 8.4.2 9.2 Field and Calculated SwitchoverJTrip Setpoint (FTSPJSP)

This calculation has determined that the existing Field Trip Setpoints (FTSP) for Auxiliary Feedwater Low Suction Pressure Alarm and.Low-Low Suction Pressure Trip should be revised to meet the setpoint acceptance criteria prescribed in Section 2.0 of this calculation.

The setpoint summary is shown in the table below.

Calculation No.97-023 1 Revision 002-C Page 6 6 of 72 9.3 Acceptable As-Left and As-Found Tolerances This calculation has determined the Acceptable As-Found and As-Left Tolerances for the instruments listed in Section 1.5. The values are rounded to the precision of the calibration procedures. The new As-Found and As-Left Tolerances should be incorporated into the affected calibration procedures identified in Section 10.0.

Refer to Section 8.5.1 for As-Found Tolerances and Section 8.5.2 for As-Left Tolerances.

Table 9.3-1 Steam Driven Pump Suction Pressure Instrumentation As-LeftIAs-Found Values I Switchover/ Trip & Alarm Bistable Units 1

Pressure IN V/I Converters Transmitters Converters 1(2)PC-4044-LL 1(2)PM-4044-3 1(2)pc-4044-~

l(2)PT-4044A l(2)PQ-4044 (Switchoverl (Alarm)

Trip)

As-Left rt 0.04 lnAdc rt 0.050 Vdc rt 0.08 mnAdc rt 0.020 Vdc rt 0.03 rnAdc As-Found rt0.lOmnAdc f:0.057 Vdc rt 0.1 1 mAdc t 0.054 Vdc rt 0.08 mAdc Table 9.3-2 Steam Driven Pump Suction Pressure Instrumentation Channel Operability Testing Rack Error As-Found Values Rack Error - Channel Operability Testing As-Left rt 0.054 Vdc As-Found rt 0.078 Vdc 9.4 Limitations 9.4.1 Computer Room Temperature Limitations The results of this calculation are valid only if the temperature inside of the Computer Room instrumentation panels does not exceed 120 OF. GAR 01031656 has been generated to traclc this limitation.

9.4.2 M&TE Limitations To preserve the validity of this calculation's results, this calculation requires that all future calibrations of the equipment (addressed in this calculation) be performed using the M&TE mentioned below (or better).

Calculation No. 97-0231 Revision 002-C Page 67 of 72 M&TE Range Accuracy Readability Reference 0.025 % reading 8.1.14, Fluke 45 (slow res.) 0-10 Vdc + 600 pV 0.001 Vdc 8.1.23, 8.1.32 0.05 % reading 8.1.3, 8.1.14, Fluke 45 (medium res.) 0-30 ~llA +3@ 0.001 mA 8.1.23, 8.1.32 0.0035 % reading 8.1.14, HP 34401A 0-10 Vdc + 0.0005 % range 0.00001 Vdc 8.1.23, 8.1.32 0.050 % reading 8.1.3, 8.1.14, HP 34401A 0-100 mAdc + 0.005 % range 0.0001 mAdc 8.1.23, 8.1.32 Ashcroft 452074SD02L 30 psig +0.25 % FS 0.001 psig 8.1.3 McDaniels 30 psig +0.50 % FS 0.05,psig 8.1.3 9.4.3 Not Used.

9.4.4 Not Used.

9.4.5 Implementation of EC-13407 This calculation has an imposed condition requiring documents P.l, P.2, P.3, P.4, D.2, D.3, D.4 and all impacted equipment to be modified to incorporate the changes per EC-13407 and minor revisions of this calculation.

Calculation No.97-023 1 Revision 002-C Page 68 of 72 9.5 Graphical Representation of Revised Setpoints and Tolerances 9.5.1 Steam Driven Low-Low Suction Pressure Trip (Bistable Only)

Steam Driven Pump Low-Low Suction Pressure Switchover I Trip Setpoint 6.26 psig (2.087 Vdc) 6.16 psig (2.053) Vdc)

FTSP 6.1 psig (2.033 Vdc) 6.04 psig (2:013 Vdc)

-As-Found 5.94 psig (1.979 Vdc)

LTSP (TS Limit) 5.8 psig (1.933 Vdc)

Calculated SP 5.759 psig (1.920 Vdc)

Analytical Limit 5.241 psig 9.5.2 Steam Driven Low-Low Suction Pressure Trip Rack Error - Channel Operability Testing Steam Driven Pump Low-Low Suction Pressure Switchover 1Trip Setpoint Rack Error - Channel Operability Testing

+As-Found 6.33 psig (2.1 11 Vdc)

+As-Left 6.26 psig (2.087 Vdc)

FTSP 6.1 psig(2.033 Vdc)

-As-Left 5.94 psig (1.979 Vdc)

-As-Found 5.87 psig (1.955 Vdc)

LTSP (TS Limit) 5.8 psig (1.933 Vdc)

Calculated SP 5.759 psig (1.920 Vdc)

Analytical Limit 5.241 psig

Calculation No. 97-0231 Revision 002-C Page 69 of 72 9.5.3 Steam Driven Low Suction Pressure Alarm Steam Driven Pump Low Suction Pressure Alarm Setpoint

+As-Found 6.75 psig (7.60 mAdc)

+As-Left 6.66 psig (7.55 mAdc)

FTSP 6.6 psig (7.52 mAdc)

-As-Left 6.54 psig (7.49 mAdc)

-As-Found 6.45 psig (7.44 mAdc)

Calculated SP 5.863 psig (7.13 mAdc)

Analytical Limit -5.241 psig

Calculation No. 97-0231 Revision 002-C Page 70 of 72 9.5.4 Technical Specification Value The requirement for the Limiting Safety System Setting (LSSS) to be in the Technical Specification is met by specifying a value in the Specificationsthat is the least conservative value that the LTSP can have during testing along with requiring that the LTSP and methodology for determining the LTSP inust be in a document controlled under 10 CFR 50.59.

Using the setpoint acceptance criteria prescribed in Section 2.0 for a decreasing setpoint Section 8.6.1 determined the LTSP to be as follows:

LTSP S ~ ~ ~ ~ T C H O ~ E R / T R ~=P5.8

-MOpsig

~O~-~~W The LTSP provided in this calculation is based upon the design of the new unitized Auxiliary Feedwater System to be installed as part of the extended power uprate (EPU) at Point Beach Nuclear Plant Units 1 and 2. The LTSP provides the information for Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, Item 6.e for "AFW Pump Suction Transfer on Suction Pressure Low". The LSSS for Function 6.e. is proposed to be 5.8 psig.

EPU Tech Spec Table 3.3.2-1 Function 6. e. contains a single line that applies to both the turbine- and motor-driven AF pumps, this minor revision and-minor revision 002-D must recommend the same setpoint values. This minor revision and minor revision 002-D recommend the same values for all setpoints for consistency.

Table 9.5-1: Input to EPU TS Table 3.3.2-1 Function Allowable Value Nominal Trip Setpoint

6. e.

' W W Pump Suction Transfer 2 5.8 psig 6.1 psig on Suction Pressure Low"

Calculation No.97-023 1 Revision 002-C Page 71 of 72 10.0 IMPACT ON PLANT DOCUMENTS Note: Passport Engineering Change (EC) Number for Calculation 97-023 1-002-C is 15802.

a PBNP-IC-42, Rev. 1, "Condensate Storage Tank Water Level Instrument Loop Uncertainty1 Setpoint Calculation" The AFP Pressure SwitchoverITrip setpoint per this calculation is input to PBNP-IC-42 for determining the CST water level instrument loop uncertainties and the adequacy of CST water level setpoints.

97-0215-002-A, Rev. 5, "Water Volume Swept by all four AFW Pumps following a Seismic

/Tornado Event affecting both Units."

To ensure that this trip initiation provides protection for the AFW pumps, the minimuin volume of 5 12 gallons in the protected piping (corresponding to EL. 24.17 feet) must be used in Calculation 97-0215 for ensuring that sufficient water (including water pumped during the associated trip time delay) is available to supply the AFPs until they automatically trip, thus preventing damage to the pump.

o lICP 04.003-5, Rev. 12, "Auxiliary Feedwater Flow and Pressure Instruments Outage Calibration" Revise procedure to include the new pressure transmitter 1PT-4044A.

e 21CP 04.003-5, Rev. 13, "Auxiliary Feedwater Flow and Pressure Instruments Outage Calibration" Revise procedure to include the new pressure transmitter 2PT-40448.

lICP 04.032-1, Rev. 15, "Auxiliary Feedwater System and Charging Flow Electronic Outage Calibration" Revise procedure to include the new As-Found Tolerances for the Steam Driven Suction Pressure Rack Components. New SwitchoverITrip and Alarm setpoints for the Suction Pressure Bistable units need to be incorporated.

6 2ICP 04.032-1, Rev. 13, "Auxiliary Feedwater System and Charging Flow Electronic Outage Calibration" Revise procedure to include the new As-Found Tolerances for the Steam Driven Suction Pressure Rack Components. New SwitchoverlTrip and Alarm setpoints for the Suction Pressure Bistable units need to be incorporated.

o STPT 14.11, Rev. 20, "Auxiliary Feedwater" New SwitchovedTrip and Alarm setpoints for the Suction Pressure Bistable unit need to be incorporated.

8" i ' Calculation No.97-023 1 S ary e

jrh dii L ~ ~ n d y ~ ~ = Revision 002-C

, Page 72 of 72

,,/

11.0 ATTACHMENT LIST Attachment A (Ref. G.6), Walkdown, Pressure Transmitter Elevation and Pressure Tap Elevation (6 pages).

Attachment B, Instrument Scaling (5 pages).

Attachment C (Ref. G. 1l), Walltdown, ICTI-621 and ICTI-797 Readability (3 pages)

ATTACHMENT A Calculation No.97-023 1 Revision 002-C Page A1 of A6 PART 1 WALKDOWN REQUEST FORM Calculation No. 97-0231 Walkdown Location (Bldg/ElevlRoom/ColumnLines)

Control Building / Elevation 8' 1 Auxiliary Feedwater Pump Rooms Scope Determine the distance between transmitters Pi-4042, PT-4043, 1PT-4044 and 2PT-4044 and their corresponding pipe centerline.

Also, determine the distance between the transmitters listed above and their corresponding pressure tap.

References:

Data Tolerance Requirements

/-

S&L w. Barasa Signature Date 5 YO -05 Lead A

PI-PB-029, ATTACHMENT 3 PAGE 1 of -

ATTACHMENT A Calculation No.97-023 1 Revision 002-C Page A2 of A6 PART 2 WALKDOWN DATA COLLECTION FORM Results See attached diagram for each pressure transmitter (4 pages total).

Signature Date Signature Date PI-PB-029, ATTACHMENT 3 PAGE 2 of -

ATTACHMENT A Calculation No. 97-0231 Revision 002-C Page A3 of A6

ATTACHMENT A Calculation No.97-023 1 Revision 002-C Page A4 of AG

ATTACHMENT A Calculation No.97-023 1 Revision 002-C Page A5 of A6

ATTACHMENT A Calculation No.97-023 1 Revision 002-C Page A6 of A6 9

"F-a

ATTACHMENT B Calculation No.97-023 1 Revision 002-C Page B 1 of B5 Instrument Scaling This calculation has determined Acceptable As-Found Tolerances for all inst~wnentsidentified in Section 1.5 iu. addition to new setpoint values and new Acceptable As-Left Tolerances for IPT-4044A and 2PT-4044A. The following tables illustrate the necessary modifications to calibration procedures P.l through P.4 to account for these new tolerance values. The boxed-in fields represent the necessaly changes; all other fields are provided for completeness only.

For lICP 04.003-5:

I EQUIPMENT ID: 1PT-4044A MANUFACTURER: Rosemount DESCRIPTION: P-29 AFP Suction Pressure MODEL NUMBER: 305lNG3A02AlJH2B2 SCALING: 0.0 - 30 psig / 4.00 - 20.00 mAdc LOCATION: El. 8', CB, AFP RM 1P-29 CUB I

ATTACHMENT 83 Calculation No.97-023 1 Revision 002-C Page B2 of B5 For 2ICP 04.003-5:

ATTACHMENT B Calculation No.97-023 1 Revision 002-C Page B3 of B5 For lICP 04.032-1 CData Sheet 5):

EQUIPMENT ID: 1PC-4044-LL MANUFACTURER: Foxboro DESCRTPTION: 1P-29 AFP Suction Header Pressure Bistable MODEL NUMBER: 2AP+ALM-AR EQUIPMENT ID: 1PC-4044-L MANUFACTURER: Foxboro DESCRTPTION: 1P-29 AFP Suction Header Pressure Bistable MODEL NUMBER: 2AP+ALM-AR Annunciator Check

,- ATTACHMENT 5 Calculation NO.97-023 1 f ',

s a ~a:LunpfyLLS

= ~ Revision 002-C

,F ' Page B4 of B5 For 2ICP 04.032-1 CData Sheet 5):

ATTACHMENT B Calculation No.97-023 1 Revision 002-C Page B5 of B5 Per Section 9.4, to preserve the validity of this calculation's results, this calculation requires that all future calibrations of the equipment (addressed in this calculation) be performed using the M&TE mentioned below (or better). This table needs to be implemented in calibration procedures l(2)ICP 04.003-5 and l(2)ICP 04.032-1 to provide the calibrator with a list of acceptable M&TE equipment.

M&TE Range Accuracy Readability 0.025 % reading +

Flulce 45 (slow res.) 0-10 Vdc 600 pV 0.001 Vdc 0.05 % reading Fluke 45 (medium res.) 0-30 mA +3pA 0.001 1nA 0.0035 % reading +

HP 34401A 0-10 Vdc 0.0005 % range 0.00001 Vdc 0.050 % reading +

HP 34401A 0-100 mAdc 0.005 % range 0.0001 mAdc Ashcroft 452074SD02L 30 psig +0.25 % FS 0.001 psig McDaniels 30 psig +0.50 % FS 0.05 psig

ATTACHMENT C Calculation No.97-023 1 Revision 002-C Page C1 of C3 1

PART 1 WALKDOWN REQUEST FORM Calculation 97-0231-002-8 Walkdown Location (Bldg/Elev/Room/Colomn tines) scope The purpose of this walk down is to provide input to Calc. 97-0231-002-8for the readability of the following M&TE equipment:

• ICTI-621 : Ashcroft 452074SD02L 30 psi Digital Gauge ICTI-797 :McDaniels 30 psi gauge Documentationwill be provided via photographs.

References:

ICI 12 Data Tolerance Requirements S&L Lead Nicholas Vilione Signature 11 , Date 5/28/2009

ATTACHMENT C Calculation No. 97-0231 Revision 002-C Page C2 of C3 PART 2 WALKDOWN DATA COLLECTlON FORM Results See photographs.

The least significant digit of ICTI-621 is 3 digits to the right of the decimal.

PAGE 2 of ATTACHMENT C Calculatio~lNo. 97-0231 Revision 002-C Page C3 of C3 IThe subdivisionsof ICTI-797are 0.lpsi.

Steven Barwin ,.-

..$%G;ZZ C?;.,,,T., ,...,.--,e 1 .- ;I-> ,..I-<>

I Independent Verifier Name Signature Date PAGE 3 of 3