ML032890050

License Amendment Request: Increase Rated Thermal Power, Response to Request for Additional Information

ML032890050
Person / Time
Site:	Palisades
Issue date:	10/06/2003
From:	Domonique Malone Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MB9469
Download: ML032890050 (97)

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Palisades Nuclear Plant Operated by Nuclear Management Company, LLC October 6, 2003 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 PALISADES NUCLEAR PLANT DOCKET 50-255 LICENSE No. DPR-20 LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MB9469)

By letter dated June 3, 2003, Nuclear Management Company, LLC (NMC), requested Nuclear Regulatory Commission (NRC) review and approval of a license amendment for the Palisades Nuclear Plant. NMC proposed to revise Appendix A, Technical Specifications, to increase rated thermal power by 1.4% from 2530 megawatts thermal (MWt) to 2565.4 MWt.

On September 10, 2003, the NRC issued a request for additional information (RAI) regarding the above license amendment request. Attached is NMC's response to the RAI.

This letter contains the following new commitments and no revisions to existing commitments:

I NMC will revise plant procedures to address operation with the plant process computer (PPC) feedwater flow indication or a PPC feedwater temperature indication out of service prior to implementation of the proposed power uprate.

NMC will revise plant procedures to include at least 0.1 % power conservatism when the UFM correction factors are established for use in the plant heat balance calculation prior to implementation of the proposed power uprate.

27780 Blue Star Memorial Highway

• Covert, Michigan 49043-9530 Telephone: 269.764.2000

I declare under penalty of perjury that the foregoing is true and accurate. Executed on October 6, 2003.

Daniel J. Malone Site Vice-President, Palisades Nuclear Plant CC Regional Administrator, USNRC, Region Il Project Manager, Palisades Nuclear Plant, USNRC, NRR NRC Resident Inspector - Palisades Nuclear Plant Attachments

ATTACHMENTI NUCLEAR MANAGEMENT COMPANY PALISADES NUCLEAR PLANT DOCKET 50-255 October 6,2003 LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 12 Pages Follow

LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NUCLEAR REGULA TORY COMMISSION (NRC) REQUEST - INTRODUCTION By application dated June 3, 2003, the Nuclear Management Company, LLC (NMC),

submitted a request to increase rated thermal power by 1.4 percent from 2530 megawatts thermal to 2565.4 megawatts thermal. This power level increase is considered a measurement uncertainty recapture (MUR) power uprate. Please provide the following additional information:

NRC REQUEST

1.

Most power uprate applications use instrument uncertainties in terms of percent power from the plant data or provided by the instrument vendor for each parameter affecting power calorimetric, and combine those uncertainties using the square root sum of squares methodology to calculate total power measurement uncertainty. This calculated power measurement uncertainty was subtracted from the 2 percent (required by 10 CFR Part 50, Appendix K) to determine the proposed power uprate.

For the proposed power uprate, NMC assumed measured values of various parameters, including feedwater flow. These assumed values from References 9.5, 9.6, and 9.10 were used to calculate power calorimetric uncertainty as per Attachment 1, "Uncertainty Calculation for the Secondary Calorimetric Heat Balance, EA-ELECO8-0001, Revision 1, to Enclosure 4 of the application. Enclosure 4 states that Crossflow system implementing procedures ensure the assumptions and requirements of the uncertainty calculation remain valid.

Please provide References 9.5, 9.6, and 9.10 for staff review. What is the plant-specific ultrasonic flow measurement (UFM) system measurement uncertainty for the assumed 11,357, 000 Ibm/hr feedwater flow with the assumption in Section 4.2.2 of Attachment 1 and how was it determined?

NUCLEAR MANAGEMENT COMPANY, LLC (NMC) RESPONSE to the June 3, 2003, application provided a calculation of the uncertainties associated with the secondary heat balance. Several plant instrument loops provide input to the plant process computer wherein the secondary heat balance calculation is performed. Many of these instrument loops are used in other applications and as such, instrument loop error analyses are contained within other engineering analyses. In order to not have the same calculation appear in multiple calculation packages, the errors associated with these loops were obtained from the existing calculation and referenced as input to the secondary heat balance calculation. To aid in the NRC staffs review of the secondary heat balance calculation, the requested references are provided as Attachments 2, 3, and 4 of this submittal.

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LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION The error associated with the UFM calculated feedwater flow is 0.44%.

This value was determined on the as-built UFM installed at Palisades Nuclear Plant using the methodology described in section 5 of Topical Report CENPD-397-P-A Revision 1, "Improved Flow Measurement Accuracy Using CrossFlow Technology." This error is further combined with errors associated with feedwater flow differential pressure (from the flow venturi) and feedwater temperature instrument loops to determine a total feedwater flow error. This total error is then used in the secondary heat balance error analysis as described in Section 3.2.3 of Attachment 1 to the June 3, 2003, application. Calculation of the total feedwater flow error using the UFM is included in Attachment 3 of this submittal.

NRC REQUEST

2.

Section 8 of Attachment 1 states that the calorimetric calculations used the plant process computer (PPC) point indications of feedwater flow and temperature. However, it also states that the control room indications of feedwater flow and temperature with larger uncertainties than the PPC point indications, may also be used in the power calorimetric. Identify the affect of using control room indication, instead of PPC point indication, on power calorimetric results used for the proposed power uprate.

NMC RESPONSE In the event that the PPC feedwater flow indication or a PPC feedwater temperature indication is out of service, then a manual heat balance calculation would be required. The larger uncertainties associated with any of these conditions will require a 100% thermal power value of 2530 megawatts thermal (MWt) in the power calorimetric. NMC will revise plant procedures to address operation with the PPC feedwater flow indication or a PPC feedwater temperature indication out of service prior to implementation of the proposed power uprate.

NRC REQUEST

3.

In Section 7 of Attachment 1, the UFM corrected total calorimetric uncertainty is listed as '=+O.49 % Power -0.55% Power" and that for the uncorrected feedwater flow (venturi measurement) is listed as "+1.13%

Power -1.21% Power." Confirm that it respectively means +0.49% or

-0.55% power and +1.13% or -1.21% power otherwise explain.

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LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER-RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NMC RESPONSE The correct interpretation of the conclusion of Attachment 1 is that when UFM corrected indicated power is 100% of rated thermal power, true power (P) is 99.45% < P < 100.49%. Using uncorrected feedwater flow, when indicated power is 100% of rated thermal power, P is 98.79% < P < 101.13%.

NRC REQUEST

4.

Item 1.G of Regulatory Issue Summary 2002-03 requires all licensees requesting an MUR power uprate to provide the basis for the proposed allowed outage time (AOT) for the UFM. Most applicants forpower uprates propose AOTs ranging from 24 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and quantify the maximum error in core power measurement due to venturi measurements during the AOT. NMC has proposed a 3-day AOT with an additional 25-percent grace period on the basis that this is currently specified in Palisades'procedures. Provide justification that the proposedAOTis not excessive and will only cause an acceptable error in core power measurement.

NMC RESPONSE The term "allowed outage time" that is specified in NRC Regulatory Issue Summary (RIS) 2002-03, Guidance on the Content of Measurement Uncertainty Recapture Power Uprate Applications," does not appropriately characterize the application of the Crossflow UFM system at the Palisades Nuclear Plant. This term is more appropriately used for plants that have a UFM system directly connected to their process computer.

NMC included this term in the June 3, 2003, submittal to correspond to the requested information in RIS 2003-03.

The Crossflow UFM system at Palisades is not connected to the PPC. It is used as an offline calibration tool to calibrate the venturi feedwater flow indication on a monthly interval. Each month the ratio of UFM feedwater flow to venturi flow is determined. From this ratio, a conservative UFM correction factor" is established that is manually input into the PPC to adjust the venturi feedwater flow measurement to the correct value. Also, a drift component of the feedwater flow transmitter is included in the uncertainty analysis included as Attachment 3 to this submittal. The procedure for completing the evaluation is treated like a technical specification (TS) surveillance and, therefore, includes a 25% grace period.

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LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION UFM correction factors have been in-use at Palisades Nuclear Plant since 1997. The original surveillance frequency was bi-weekly. After 3 1/2 years of operating experience, the surveillance period was increased from bi-weekly to monthly beginning with cycle 16 in May 2001. Since May 2001 there has been two instances where the calculated UFM correction factor was non-conservative with respect to the amount of correction applied in the heat balance calculation. The amount of non-conservatism in both cases was approximately 0.01 % power (0.25 MWt). Neither case resulted in a violation of the licensed power level for the Palisades Nuclear Plant. From February 2002 to January 2003, the average calculated UFM correction factor change was approximately 0.05% power per month. In the two cases described above, the amount of conservatism (difference between the calculated correction and the value applied in the heat balance calculation) in the applied UFM correction factor was approximately 0.07% power. This was less than the 0.1%

power conservatism typically applied by NMC to account for data scatter that can be seen in the UFM calculation from month to month. Since the second instance of being slightly non-conservative, at least 0.1% power conservatism has been included in determining the UFM correction factors that are applied to the heat balance calculation. NMC will revise plant procedures to include at least 0.1% power conservatism when the UFM correction factors are established for use in the plant heat balance calculation prior to implementation of the proposed power uprate.

Administrative controls exist to provide assurance that only acceptable errors in core power measurement occur between performances of the formal surveillance. For example, if the plant would be required to reduce power below 95%, procedural guidance is provided to remove the UFM correction factors from service. Once power is restored to near 100%

then the UFM correction factors are recalculated to ensure that no changes have occurred due to the plant transient. In addition, Hi and LO steam flow alarms on the PPC monitor for unanticipated changes in steady state reactor power between performances of the formal surveillance. These indications are provided on each steam generator and provide continuous monitoring of steam flow. The steam flow alarm setpoints are determined during the monthly determination of the UFM correction factors. Plant procedures describe actions required in response to Hi or LO alarms or PPC inoperability. For example, if a Hi steam flow alarm actuates and the cause is not known (i.e., not an instrument failure, etc.), plant power is reduced to the point where UFM correction factors may be removed from service. Also, if the PPC becomes inoperable and the continuous monitoring feature is lost, then daily verifications of the UFM feedwater flow is performed to verify no significant changes have occurred and that the UFM correction factors are still applicable. In general, if at any time a required UFM correction factor 4

LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION verification cannot be performed when required by procedure, then power would be reduced and the UFM correction factors would be removed from service.

NRC REQUEST

5.

Provide, in detail, the effect of the proposed power uprate on the environmental qualification of electrical equipment.

NMC RESPONSE The proposed power uprate has no effect on the Palisades Nuclear Plant environmental qualification (EQ) program. The EQ evaluation parameters assume reactor power of at least 2580.6 MWt, 102% of the current rated thermal power of 2530 MWt. Therefore, the programs, activities, elements, and philosophy that are currently in place are not affected by the proposed 1.4% power uprate. No physical change to the facility is necessary; therefore, no equipment reviews are required.

NRC REQUEST

6.

Provide details about the grid stability analysis, including assumptions, results, and conclusions for the proposed power uprate condition.

NMC RESPONSE The purpose of the grid stability analysis is to document the Palisades Nuclear Plant licensing basis concerning plant stability and the reliability of offsite power. The analysis reflects the near term system conditions including scheduled system additions following completion of several major new power plants connected to the Michigan Electric Transmission Company (METC) system. New generation includes the Covert Generating Station, approximately one mile east of the Palisades Nuclear Plant, which is connected to the Palisades Nuclear Plant Substation. The study also includes the Zeeland Power Plant (connected to the 345kV transmission line between the Palisades and Tallmadge stations), the Jackson Power Plant, and the Renaissance Power Plant.

The analysis was performed using a power flow computer simulation of the Consumers Energy operating system including interconnections to other utilities. The computer simulation contains detailed models representing the Consumers Energy 46kV and higher voltage systems, the International Transmission Company (ITC), Detroit Edison (DECO) high voltage transmission system, and other East Central Area Reliability (ECAR) Council member full transmission representations or 5

LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION equivalents. The study was based on both peak load and 80% peak load cases. The analysis covered the range of expected power imports into the METC from 4000 to 6000 MW.

Two specific offsite power supply criteria analyzed in the study to which Palisades was originally licensed are:

A. The sudden loss of the Palisades Nuclear Plant electrical output will not result in instability of the offsite power system.

B. A sudden 1000 MW drop of system load will not adversely affect the Palisades Nuclear Plant or the connected electric system.

The stability of the Palisades offsite power system was evaluated for the following situations:

METC's Planning Criteria Disturbances (Includes various phase-to-ground faults in the switchyard)

Sudden Loss of 1000 MW of Load Sudden Loss of the Palisades Generating Unit The analysis resulted in the following conclusions:

The Palisades Nuclear Plant and the offsite power system connected to Palisades Substation are stable for:

o A three phase-to-ground fault, anywhere in the system, which will be cleared by primary relays and all transmission in-service before the disturbance.

o A three phase-to-ground fault, anywhere in the system, which will be cleared by primary relays with the most critical element out of service before the disturbance.

o A two phase-to-ground fault with subsequent breaker failure, anywhere in the system, with all transmission in service before the fault.

o Inadvertent tripping of three Ludington units in the pumping mode, representing a 1020 MW of sudden load drop, or for sudden loss of 1000 MW of area load.

The offsite power system connected to Palisades Substation is stable for inadvertent tripping of the Palisades or Covert Plant units.

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LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION The Covert Generating Station is rated at 1185 MWe and is connected to the Palisades Substation. Since the Covert Generating Station's output exceeds Palisades output, the transient resulting from the Covert Station tripping offline bounds the transient that would result from Palisades tripping even for Palisades power levels above the proposed power uprate.

NRC REQUEST

7.

Provide, in detail, the effect of the proposed power uprate on the station blackout coping capability.

NMC RESPONSE The evaluation of a station blackout event for the Palisades Nuclear Plant was performed in accordance with the requirements of Regulatory Guide 1.155, Station Blackout." This evaluation determined an acceptable station blackout duration for Palisades of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This 4-hour coping duration was based on the reliability and configuration of the off-site power system and the reliability of the diesel generators. To provide assurance that the plant could cope with a station blackout of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duration, several factors were considered. These areas included the following:

Condensate Inventory Class 1 E Battery Capacity Compressed Air Effects of Loss of Ventilation Containment Isolation Reactor Vessel Inventory NMC has determined that the only factor potentially affected by the proposed power uprate is the condensate inventory required to provide decay heat removal for the 4-hour duration.

The station blackout analysis was approved in a letter from B. Holian (NRC) to G.B. Slade (CPCo), Palisades Plant Station Blackout Analysis; Safety Evaluation (TAC No. 68578)," dated May 20, 1991. In that safety evaluation, the NRC calculated the minimum condensate inventory based on a power level of 102% of 2530 MWt (2580.6 MWt). This minimum inventory was determined to be 57,100 gallons. Palisades TS require maintaining an inventory of 100,000 gallons. Therefore, the proposed power uprate has no effect on the station blackout coping capability.

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LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC REQUEST 8.

Provide, in detail, the existing ratings and the effect of the proposed power uprate on the following equipment:

main generator isophase bus main power transformer start-up transformer station power transformer NMC RESPONSE The table below provides the requested information. Note that the proposed power uprate has minimal impact on the electrical equipment at the plant. Following the 1.4% proposed power uprate, the plant output will remain well below the design rating of the main generator. The major effect will be a slight reduction in the capability to provide volt-amps reactive (VARs). The proposed power uprate has virtually no impact on the isophase bus, main transformer and startup/station power transformers.

Electrical Equipment Information Aniticipated Design Current Vae Equipment' Rating Value Value 955 MVA 823 MWe2 834.5 MWe2 Main Generator 22 kV 22 kV 22 kV 0.85 power factor 0.86 PF 0.87 PF

________________________(PF)

Isophase Bus 26,400 amp 25,0623 25,0623 Main Transformer 975 MVA 955 MVA 3 955 MVA 3 12.6 MVA 11.6 MVA 11.6 MVA Station Power4 Transformer 1-1 12.6 MVA 11.7 MVA 11.7 MVA Station Power Transformer 1-2 8.96 MVA 8.4 MVA 8.4 MVA 12.6 MVA 10.0 MVA 10.0 MVA Station Power4 Transformer 1-3 12.6 MVA 10.0 MVA 10.0 MVA 12.6 MVA 12.2 MVA 12.2 MVA Startup Transformer 1-1 12.6 MVA 10.0 MVA 10.0 MVA 8

LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Design Current Anticipated Equipment1 Rating Value (1.4% Uprate)

Startup Transformer4 1-2 10.6 MVA 6.9 MVA 6.9 MVA 12.6 MVA 11.9 MVA 11.9 MVA Startup Transformer 4 1-3 12.6 MVA 10.0 MVA 10.0 MVA Safeguards Transformer 10.5 MVA 9.0 MVA 9.0 MVA Notes: 1. Equipment ratings based on 650C temperature rise.

2. MWe output based on the yearly average East Central Area Reliability (ECAR) Council rating and includes 38 MWe house loads.

3. The maximum rating of the isophase bus and main transformer exceed the design output rating of the main generator.

4. These transformers have dual secondary outputs.

NRC REQUEST

9.

Upon reviewing large-break loss-of-coolant accident [LOCAl models for power uprates, the Nuclear Regulatory Commission (NRC) recently found plants that require changes to their operating procedures because of inadequate hot leg switch-over times and boron precipitation modeling.

Discuss how NMC's analyses account for boric acid buildup during long-term core cooling and discuss how your predicted time to initiate hot leg injection corresponds to the times in Palisades' operating procedures.

NMC RESPONSE The Palisades long-term cooling (LTC) analysis (hot leg switch-over times and boron precipitation modeling) was performed by Combustion Engineering using the NRC approved methods described in CENPD-254-P-A, Post-LOCA Long Term Cooling Evaluation Model."

Palisades plant specific analysis (P-CE-5627 dated May 8, 1981) was sent to Dennis Crutchfield, NRC, on October 9, 1981. Conservative plant operating parameters that increased core boron concentration and a core power level of 102% of 2530 MWt were used in the analysis.

In evaluating the LTC performance for the large break LOCA, the limiting break with respect to long-term boric acid accumulation in the reactor vessel is the double-ended break in the reactor coolant pump discharge leg. This break is most limiting because it has the smallest margin between the calculated maximum boric acid concentration and the associated precipitation limit of 32 wt% (solubility at 228 0F which is the saturation temperature at 20 psia). Core flushing flow provided by the 9

LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION simultaneous hot side and cold side injection from a high pressure safety injection pump reduces the boric acid accumulation. The analysis maximizes the core boric acid concentration by assuming that only steam leaves the core. Sensible heat removal due to liquid flush when it occurs is always neglected. Charging pump flow from the boric acid storage tank (BAST) is deposited in the vessel before any consideration is given to other sources of boric acid. Also, the initial boric acid concentration in the vessel for large breaks is conservatively assumed to be equal to the safety injection tanks (SIT) or safety injection and refueling water (SIRW) tank concentration, whichever is higher.

The current administrative limit for the concentrated boric acid storage tanks is 8 wt% (13,987 ppm), which is less than the 12 wt% (20980 ppm) assumed in the LTC analysis. This higher value for boron injection into the vessel offsets the current higher TS limits for boron concentrations in the SIRW tank and the SIT tanks of 2500 ppm. The value used in the LTC analysis for SIRW and SIT tanks was 1.13% (1975 ppm). Since core boil-off is first replaced by charging pump flow from the BAST and then from the safety injection flow from the SIRW tank, the LTC results bound current Plant operation.

The results from the analysis concluded that there should be approximately 50/50 split between the hot leg and the cold leg injection paths and that the switch to long term cooling should occur between 5.5 and 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The initiation of hot and cold side injection between 5.5 and 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> post-LOCA is after any potential for hot leg entrainment has been terminated and more than 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> prior to the time which boric acid precipitation is predicted to occur if no core flushing flow is provided. The flow split is verified by a plant surveillance procedure. The LTC start time is controlled by plant Emergency Operating Procedures (EOPs).

The plant operating parameters used in the LTC analysis are equivalent with the expected Plant operating parameters following the proposed MUR power uprate. The analysis methodology maximizes the boric acid concentration in the core for the limiting cold leg break. The plant surveillance procedures and the EOPs are consistent with the LTC analysis. Therefore, the current LTC analysis remains valid for the proposed MUR power uprate.

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LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER-RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC REQUEST

10.

In the June 3, 2003, application, NMC indicates that all the accident and transient analyses of record remain bounding for the proposed power level. However, the NRC staff notes that when calculating departure from nucleate boiling (DNB), licensees typically use nominal power levels.

These power levels typically do not bound the MUR uprated power levels. Provide the core power levels and the power uncertainties used in NMC's DNB analyses and explain why these input values bound the proposed power uprate.

NMC RESPONSE Statistical minimum departure from nucleate boiling ratio analyses were performed for the current operating cycle (cycle 17) transient analyses at a nominal power level of 2565.4 MWt with a power uncertainty of 2580.6 MWt - 2565.4 MWt = 15.2 MWt, which is 0.6% of 2530 MWt, in accordance with the currently approved methodology.

NRC REQUEST

11.

As stated on page 15 of Enclosure 4, axial and circumferential outside diameter stress-corrosion cracking (ODSCC) at the hot leg top of tubesheet are two of the six active damage mechanisms that have been identified in the steam generator tubing at Palisades.

On page 16 of Enclosure 4, NMC indicates that ODSCC at the top of the tubesheet has the greatest potential to be affected by the slight increase in Th. (which will occur due to the power uprate). However, the NMC concludes that the onset of this damage mechanism will not occur until after the end of the license.

The information on these two pages conflicts. Please discuss the discrepancy and clarify whether ODSCC at the top of the tubesheet has been identified in the Palisades steam generator tubing, and what the impact of the proposed power uprate will have on this damage mechanism.

NMC RESPONSE NMC acknowledges the discrepancy, which was not identified during the submittal review and approval process. This condition has been entered into the site corrective action process.

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LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION The following statements on page 16 of Enclosure 4 of the June 3, 2003, application no longer apply:

"A curve developed by the Electric Power Research Institute (EPRI), in conjunction with the 1999 refueling outage, predicts that the onset of this damage mechanism will not occur until after the end of the license. Since the T. value used in constructing the curve is the same Tt value expected at proposed uprated conditions, the proposed uprate would not change this conclusion.'

The following discussion replaces the statements above:

During the 2003 refueling outage, circumferential ODSCC at the hot leg top of the tubesheet and axial primary water stress corrosion cracking (PWSCC) within the expanded tubesheet region were identified as new active damage mechanisms. These new active damage mechanisms, as well as axial ODSCC at the hot leg top of the tubesheet, are affected by time and temperature, but not by an increase in secondary side steam flow. T at Palisades of 582.70F is low for Alloy 600 tubing per existing industry experience, and a 0.30F increase is expected to have a negligible effect on these new active damage mechanisms. The greatest effect will be seen on mechanical tube wear.

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ATTACHMENT 2 NUCLEAR MANAGEMENT COMPANY PALISADES NUCLEAR PLANT DOCKET 50-255 October 6, 2003 LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

REFERENCE 9.5: EA-AFZ-96-01, Analysis of Various Heat Balance Input Inaccuracies," Revision 2 13 Pages Follow

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IF#J PoMcr Palisades Nuclear Plant fIwe ENGINEERING ANALYSIS COVER SHEET EA AZ-96 -1 Total Number of Sheets 12 ie Analysis of Various Heat-Balance Input Ina INITIATION AND REVIEW Calculation Status Preliminary Pending Final Superseded O

0 a30 Initiated Int Review method Technically Reviewed Revr Rev Appd Detail ual Apprd CPCO Descnption By Date By Alt Cac Review Test By Date By Appd 4-18-96 SW DM 4129196 OOC 0

Original Issue AFZillins X

Kennedy 1

Skip the Rev # due to possible typo confusion on Rev 0 Resolve initial S&L comments AFZillins 516-96 t

1.0 O BJECTIVE.......

... =.=-.

.=.=

2

2.0 REFERENCES

E 2

3.0 ATTACHMENTS MAY-0 199S 2

.0 ANALYSIS INPUT

2.

5.0 ASSUMPTIONS..

3 6.0 ANALYSIS...........

3 6.1 Instrument Uncertainly and Calibration Methodoloa 3

6.2 PPC contribution to Feedwater Flow and Temgerature instrument uncertainties.

4 6.3 Primary Coolant oumo instrument uncertainties relative to Heat Balance 5

6.4 PPC Comoutational Accuracy as it relates to Heat-Balance...

6 6.5 PT-07518 PT-0752B) Steam Gen Pressure as it relates to the Heat-Balance

. 6 6.6 Steam Generator Bottom Blowdown Flow as a function of Heat-Batance.................

........... 7 6.7 Letdown and Chargina Flow as it relates to the Heat-Balance...........

....... 8 6.8 Letdown Temperature Instrument Uncertainties relative to Heat Balance.......

... 11 6.9 Pressurizer Heater instrument uncertainties relative to Heat Balance...........

1...1.......

.. 11 6.10 Charging Line Temoerature instrument uncertatntfes relative to Heat Balance.......

. 12

7.0 CONCLUSION

..... 13

EA -AFZ-96-O1 ca

! Otto PALISADES NUCLEAR PLANT OW ANALYSIS CONTINUATION SHEET Sheet 2

Rev#

2 Mm Reference, Comments 1.0 OBJECTIVE The purpose of this EA is to analyze and document various Heat-Balance input and calculation uncertainties that are necessary for an overall Heat-Balance uncertainty calculation. The scope of this EA includes the following only:

PPC contribution to Feedwater Flow and Temperature instrument uncertainties Primary Coolant pump instrument uncertainties relative to Heat Balance PPC Computational Accuracy as it relates to Heat-Balance Steam Gen Pressure as it relates to the Heat-Balance.

Steam Generator Bottom Blowdown Flow instrument uncertainties as a function of Heat-Balance Letdown and Charging Flow instrument uncertainties as it relates to the Heat-Balance Letdown temperature instrument uncertainty relative to the Heat-Balance Pressurizer Heater instrument uncertainties relative to PPC input and Heat Balance Charging line temperature instrument uncertainty relative to the Heat-Balance The inaccuracies analyzed are relative to performing a Heat-balance via Palisades Plant Computer (PPC) system inputs or by manually reading instrument indicator. The overall Heat-Balance uncertainty Calculation is not within the scope of this EA.

The major contribution to the Heat balance is from Feedwater flow which is analyzed in the TSSP Basis document RI-24 and is not within te scope of the EA.

2.0 REFERENCES

I Ven. Man., MI-PA sh 1558, DALCAL tech. Manual 2

Ven. Man., MI-PA sh 1557, Universal Analog Input card set Tech. Manual.

3 Ven. Man., MI-PA sh 1553, G2" Controller User Manual 5

E-2 sh 3. Generator and 4160 volt system 6

AE Buyers Guide, Instrumc.-t Transformers 7

NUREG/CR-3659,...Model for assessing the uncertainties of Instrumentation.. For Power...

8 Tech. Spec. Surv. Proc. RI-S. Steam Gen. Pressure Channel Calibrations 9

Tech. Spec. Surv. Proc. RI-2, Primary System Temperature Calibrations 10 Ven. Man., M-I HK-2, Instruction Manual for Rosemount 1151 transmitter 11 Ven. Man., M-206-205, Instruction Manual for Rosemount 3051 transmitter 12 Calsheet Database for Installed Plant Equipment (IPI) 13 DEC Fortran User Manual, P/N AA-PUYPA-TE 14 Directrol Multiplexor, Tech. Info. Publication, Analog Input Module 15 M l-W sh 3-6, CFM Electrical Bill of Material 16 E-3 sh 1, 2400 volt system 17 ISA-RP67.04-Part 11-1994, Methodology for the Determination of Setpoints... nstrumentation 18 Square D catalog, CLE-20000 series transducers 19 ASME repot Fluid Meters, Their Theory and Application, sixth edition, 1971.

20 Burns Engineering Inc., Resistance Thermometers for all Environments 21 W024416159 calibration sheets associated with PPAC PCS01 3.0 ATTACHMENTS None 4.0 ANALYSIS INPUT All References and Attachments provide analysis input into this Engineering Analysis.

-T 7 -

-_.,.- ---- -,-.Z--.-,1 EA -AFZ 01 PALISAbES NUCLEAR PLANT Pew ANALYSIS CONTINUATION SHEET Sheet 3

Rev#

2 Reference, Comments 5.0 ASSUMPTIONS Vendor instrument Specifications are two sigma values.

Ref 7 6.0 ANALYSIS 6.1 Instrument Uncertainty and Calibration Methodologv Palisades typically performs loop calibrations and does not calibrate each loop component individually.

Limits are established for As-Founds as part of this calibration program. These As-found limits are conservatively set in relation to the as-left calibration tolerance to account for instrument drift and reference accuracy. The As-founds historically have been shown to bound the drift and other related inaccuracies associated with instrument loop calibrations. Therefore, As-found limits have been shown to conservatively bound the overall accuracy of a loop with the exception of temperature and pressure related factors. For instrument loops having As-found calibration data. the limits of the As-found's is used as the loop inaccuracy. Other uncertainties due to environmental or other effects are added to the As-found inaccuracy where required.

This EA may need to be re-evaluated or revised if configuration of analyzed instruments/loops is modified.

Other errors considered in addition to As-found limits are sensor accuracy (e.g. RTDs and flow elements).

and M&TE accuracies.

Uncertainty calculations will be performed following methods of ISA standard RP67-04 and NUREG/CR-3659. The most applicable aspect of these standards is the use of the Square Root Sum of the Squares ref 7,17 (SRSS) method of determining the total uncertainty of independent random uncertainties. Another is the method for determining the error associated with a flow related transfer function.

Where applicable, analog meters are assumed to be readable to V2 of the smallest division. This is a general convention at Palisades.

Where calibration or Vendor documentation is unavailable. typical error values will be used. These typical errors will be multiplied by at least a factor of 2. This should be conservative enough to cover unknown factors or less than perfect configurations. As there is a relatively small number of unknown instrument errors and these instrument make a relatively small contribution to the heat-balance, these estimations cannot have any significant impact on the total heat-balance uncertainty.

Per ISA-RP67.04, independent instrument uncertainties which are less than 1/5 of the largest error are ref 7 insignificant and therefore do not need to be accounted for in SRSS error calculations.

Power supply voltage effects are typically very small (on order of 0.002% of span per volt deviation).

This almost always works out to less than 1/5 of the largest error and therefore does not need to be ref 7 accounted for in SRSS error calculations Plant computer A/D Temperature effects we negligible and will not be addressed in individual instrument uncertainties. 3 of the 4 PPC multiplexors are located in the control room which maintains a near constant temperature. Three of four multiplexors including the one multiplexor outside the control room are see 6.2 temperature effect limited by their DALCAL reference card which has a maximum temperature coefficient of *IOppmP/C or.00I1%/,1.C. This effect is too small to be significant for any instrument uncertainty calculation.

V7- -1 __1 -, -.7 IM. I

.r

-inr n

-Ir 7 r 4"-

kE FZ 01 tOAL[S4lDES NUCLEAR PLANT POW W aANALYSIS CONTINUATION SHEET Sheet 4

Rev#

2 Reference.

Comments Plant computer Dead-band effects are negligible and will not be addressed in individual instrument uncertainties. Only the G2vx based multiplexors uses an input dead-band to limit data traffic. This dead-band is set to one bit for all points. One bit in 2' is equal to 0.006%. This value is to: small to be of any significance.

6.2 PPC contribution to Feedwater Flow and Temperature instrument uncertainties Note: This calculation is for input to Basis document RI-24 instrument uncertainty calculations. This should not be considered a completed calculation of instrument uncertainty.

Flow transmitter inputs:

The Transmitters are FT-0701 and FT-0703. The corresponding PPC inputs are FT_0701_DAVG and FT_0703_DAVG respectively. The engineering range for these inputs is 0 to 213.9 and 0 to 219.5 inches respectively. These are input to a Computer Products Based data acquisition system. The Analog to Digital ref 1.2.3 converter along with a online calibration loop-back feature (DALCAL) provides an accuracy of 0.01% of the input card full scale range. Temperature effect is insignificant per section 6.1. Drift is less than 0.01% of full scale per year. Adjusting this accuracy to account for the portion of the analog card's full scale range occupied by the Flow transmitter's range, gives 0.025% for accuracy and 0.025% per year for drift limit. Adjusting the drift for a 18 month calibration cycle gives 0.038%. The sense resistor utilized by the PPC for these ref 15 instruments has an accuracy of 0.25% or better.

=

ID 2 +A/D2

+Sense Resistor2 C sa cy fdwtr Raw ace drift icc

= /.0252+.0382+.252

=.25%

Note: Uncertainty error

=

.55 inches associated with the

.3xl06 PPH @ 430'F Square Root transfer function and flow element are addressed in the Flow error analysis of Basis document RI-24 Temperature Transmitters inputs:

The transmitters are fT-0706A and Tfl-0708A. The calibrated range is 0 to 500 F. The corresponding PPC inputs are TT_0706A_AVG and TT_0708A_AVG respectively. These are input to a Computer Products Based data acquisition system. The Analog to Digital converter along with a online calibration loop-back feature ref 1,2,3 (DALCAL) provides an accuracy of 0.01% of the input card full scale range. Temperature effect is insignificant per section 6.1. Drift is less than 0.01% of full scale peryear. Adjusting this accuracy to account for the portion of the analog's card full scale range occupied by the Temperature tansmitter's range, gives 0.02% for accuracy and 0.02% for drift limit. Adjusting the drift for a IS month calibration cycle gives 0.03%.

The sense resistor utilized by the PPC for these instruments has an accuracy of 0.25% or better.

e V1 I

I EA-AFZ..96 -01 I-PALISAbES NUCLEAR PLANT I ftr ANALYSIS CONTINUATION SHEET

alaI, Bss Sheet 5

Rev#

2 Reference, I Comments PPC MCUrCK% dwr lmp

i/D 2 +AD 2

+Sense Resistor2

=V.022.o32 +,252

=.25%

=

• 1.3 F

6.3 Primary Coolant pump instrument uncertainties relative to Heat Balance The PPC points are CURCPIA. CURCPI B. CURCP2A. and CURCP2B. These associated ammeters are EAI-2103. EAI-2203, EAI-2104. and EAI-2204 respectively.

Circuit

Description:

A Current Transformer (CT) on one phase of each PCP feeds a Ammeter and an 1,1 converter in the control room. The En converter in turn is run through a resistor to create a voltage which is input to one of the PPC Multiplexor Nodes. The calibrated span is 0 to 800 amps.

Instrument Errors:

ref 5 Current Transformer:

Current to Current Convertor:

PPC Accuracy:

No vendor or accuracy data could be found on this particular CT. However, per the Electrical System Engineer, this a fairly typical type of CT device. Other CTs with the same ratio of 800/5 have a worst case accuracy on the order of 0.6%. There is no calibration associated with this device. As this is a passive device, no drift should be expected. To be conservative, this error will be doubled. This works out to 1.2%

uncertainty.

This is a Square-D. cat. No CLE-202001, converter. The catalog stated accuracy is 0.25%.

This device is not calibrated. The four converters were calibrated in 1995 under a WO request. To account for the lack of libration, the catalog stated error will be tripled.

This works out to 0.75% uncertainty. Discrepancies between channels or between the PPC and meters beyond this should be noticeable by the operators.

The only significant factor for this PPC input accuracy is the sense resistor. Those bought for the CFMS modification were typically 0.025%. The Cutler-Hammer multiplexor is accurate to 0.04% fom 20 to 30 'C. As these error are significantly less than 115 of the largest error, they are insignificant for this instrument uncertainty.

ref 5 ref 6 ref 15 ref 18 IRef 15 ref 7

t~ - -

I

-I EA -AFZ 01 eo*sllXx i

PALISADES NUCLEAR PLANT PIJ muANALYSIS CONTINUATION SHEET Sheet 6

Rev#

2 Reference.

Comments Meter:

This meter is calibrated per PPAC PCS0 11 every two years or Refout. Tolerance is *3% full scale.

This meter face is graduated in 20 amp increments. There is a large distance between increments ref 21 such that the meter can be easily resolved to +/- 5 amps or *.625%

observed Total Error relative to PPC:

= lz 72

=1.22 +*752

= 1.42%

=

• 11 amps Total error relative to manual 2

2 reading:

T./CT.

+Metercc Meter,,.dbi,Y

=,l.22 2 6252

=3.29%

= +/- 26 amps 6.4 PPC Computational Accuracy as it relates to Heat-Balance The PPC has two computers which pley a part in handling inputs and performing calculations related to the Heat-Balance. These are the G2-input nodes and the Host computer system. The input nodes convert the Ref 2 analog to digital converter's 14 bit numerical value to a usable engineering unit value which is then sent up to the host for alarm processing, storage, and distribution. 14 bits is equivalent to approximately 5 digits of ref 14 precision. Several points come in through the 12 bit Cutler-Hammer multiplexor and are converted to engineering units by the Host directly. Several calculated points are derived from the G2-data such as Feedwater density and density compensated flow.

Both the G21 and the Host computer handle math the same way and are subject to the same computational errors. The G2-and the Host are based on the Digital Equipment Co. VAX architecture. All conversion and computations are performed using Floating point math. The minimum floating point storage size is 4 bytes or commonly referred to as REAL*4. Per the VAX FORTRAN manual, REAL*4 number have approximately 7 ref 13 digits of precision. Floating-point math is carried out to a precision greater than the operands and thereby adds no significant round off error.

The accuracy of the Plant computer is several orders of magnitude greater than the resolution of any input or displayed output. Therefore, PPC conversions, math, and numerical precision add no significant error to the heat-balance or its inputs. A/D error is accounted for in each instruments uncertainty calculation. A/D temperature effects are addressed in section 6.1.

6.5 PT-075I B (PT-0752B) Steam Gen Pressure as it relates to the Heat-Balance These transmitters are calibrated i: TSSP rI-05. Control Room meters PIC-0751B, PIC-0752B and PPC Ref 8 points PT075 I B, PT0752B are also checked i, *h s procedure. This is a loop end to end test. The range of these transmitters and inputs is 0 to 1200 PE.

The meters have an as-found tolerance of *20 PSIA (1.7%).

The PPC points have an as-found tolerant.; )f *20 PSIA (1.7%). However, it is points PT_07051B and PT07052B which are used in the Heat-lalk nce. These are input through separate sense resistors and multiplexors. Both sets of inputs use the 3aw. e conversion constants. A comparison of inputs shows that the Heat-Balance points are reading 6 PSI (.S%; ess than the points checked in RI-5 at 99.6% power.

s= _ r v z s w _ r _ w > x x he r To _ r., w _ _ _ _ a Or _

I ~~ay e

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9-

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.r-n 1APALISAES NUCLEAR PLANT nUPM ANALYSIS CONTINUATION SHEET AEM FMOMS EA. AFZ 01 Sheet 7

Rev#

2 Reference, Comments The difference between the two sets of PPC inputs is mostly a function of different input module impedance.

The isolation resistors in conjunction with the impedance of the PPC's input module form a voltage divider network which drops enough signal voltage to see a '/2 percent lower value on the PPC. Adding.5% to the As-found tolerance in RI-5 gives a conservative error value for the steam gen. inputs used by the Heat-Balance calculation.

During a manual calculation or if these points are unavailable on the PPC. the four steam generator pressure channels for each steam generator are averaged together. These averaged values should be more accurate than the individual channels used by the PPC. As such, the error associated with one channel will bound the averaged error and will be used for this error calculation.

M&TE Error:

Transmitter drift Error Transmitter Temp. Effect:

Head Pressure Effects:

As this is loop end to end test, only M&TE error should normally be added to the total error. A DMM and pressure gage are used in the Loop end to end calibration. Both have an inaccuracy less than +/-2 psi. Since these M&TE errors are less than 115 of the largest error (Temperature effect is *28 psi), they are not significant.

Drift error is *3.6 psi over 30 months. Since this error is less than /5 of the largest error (Temperature effect is *28 psi), it is insignificant.

Per RI-5 basis, Temperature effect error is (.75% URL +.5%span)/lO0F. URL is 3000 psi and Span is 1200 psi. This works out to *28.5 psi or 2.4% of the span range.

Head pressure has been accounted for in the calibration procedure.

ref 8 Ref 8 Ref 8 Ref 8 observed meter Meter Readability: These meters are graduated in 20 PISA increments. These meters are little high on the panel and have a curved surface. We will assume that they can be read to

• 20 PSIA.

PT-075 1 B/PT-0752B total accuracy:

(relative to PPC heat balance)

= +VAs Foundppc,

Temp Effect,,

PCb.A,

= *V20 2

+ 28.52 - 6

= *35 -6 PSI PT-075IB/PT-0752B total accuracy:

(relative to meter and manual heat balance)

• Vs Found2.m.

+ Temp Effect.2,, + Meter.2, 7

= *1202 + 28.52 + 202

=

• 40 PSI 6.6 Steam Generator Bottom Blowdown Flow as a function of Heat-Balance Equipment ID:

FI-600IAIFI-6001B These inputs are read locally and then manually entered into the Heat-Balance calculation. This is a local rotometer type flow indicating device. Range is 0 to 60 KPPH. The Flow indicator is calibrated per IPI Fl-6001A on a two year cycle as scheduled by PPAC MSS008.

7? -:,. '.-7_'

f <- M =.

I

,t.

PALISAt)ES NUCLEAR PLANT I

rM ANALYSIS CONTINUATION SHEET ImXW ranEw EA -AFZ 01 Sheet 8

Rev#

2 Reference, Comments I.----..-

The indicator for these devices have different resolutions depending on the flow range. Graduation increments decrease in value as flow increases. Typical readings are in the medium and high range. The medium range's resolution and accuracy bound the higher range. It's tolerance will be used for this error calculation.

Resolution or readability is assumed to be 1/2 of the medium range graduation or 0.833% of span.

FE600I A/B:

Orifice type. No calibration data or accuracy specification could he found for this flow element. To be conservative, we will assume a calibration span error value equivalent to three time the readability of the meter in the medium range. This works out to 3/2 of one division or 2.5%.

Ref 12 Fl-6001 A/B tolerance:

As-Found dmR

2 divisions

2 KPPH

=

3.3 %

ref 12 M&TE In:

Error:

0- 1000H,0 gauge+.1%or l"H 20 500 = 00% of range. Error =.1 %

1000/500 =.2%

per M&TE cal. tag TOTAL ERROR =

=M& TE 2 +F12 FE2 + Meter 2 heVr err err readablliqy

= 22 +3 32+2.52 +0.8332

=

4.23%

(

2.5 KPPH) 6.7 Letulwn and Charging Flow as it relates to the Heat-Balance These transmitters are calibrated in PPAC CVCO35. Letdown Flow is FT-0202. Charging Flow is FT-0212.

PPC input point FT0202 has a range of 0 to 160 GPM for a 4 to 20 ma signal input. PPC point FT0212 has a range of 0 to 140 GPM for a 10 to 50 ma signal input.

ref 12 Circuit

==

Description:==

M&TE error:

Transmitter:

Temp. Effect:

FT0202 feeds a signal to FIC-0202 and to the PPC multiplexor through a precision 250 ohm 0.025% resistor. FT0212 feeds a square root device which in turn feeds FIA-0212 and the PPC through a 100 ohm 0.025% resistor.

DMM and pressure source are accurate to better than.1% which is less that 1/5 of largest error and are therefore insignificant.

Both transmitters have as-found tolerance of *0.32 ma. This works out to

• 2.00% error.

FT0212: The ambient temperature effect is

• 1.0% span per 100 F. Ambient temperature is approximately 80'F. Will assume a 30'F delta from calibration temperature. Temp.

effect works out to 30/100 1.0% = 0.3% span. As this is less than 15 of the largest error it is insignficant.

Ref 15 typical of tolerances ref 12 ref 10 FT0202: The ambient temoerature effect is *(0.025% URL +0.125% span) per 50'F.

Ambient temperature is approximately S0F. Will assume a 30'F delta from calibration temperature. Temp. effect works out to 30/50 ( 0.00025*250" +.00125*100") =0.188" H20 or 0.188% of span. As this is less than 1/5 of the largest error it is insigpficant.

ref 11

=D a

l l

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-a

r

r.

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,,v;

~ ~ ~ - -,' -i - z-

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-1 : q-sr in-u

~ss

. 4Btm' Ad AS~

ALISAbES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET EA - AFZ 01 Sheet 9

Rev#

2 I I.

I4

-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

Static Press Effects:

Flow Element Error:

Sqrt Transfer function FT02 1 2: The zero error is

• 2% of URL for 4500 PSI. This works out to 2% of span (.02

• 750"/400" '* 2500/4500). Span error is +.25% of reading per 1000 PSI. Error at typical reading of 9% of Dp span is 0.06% (.25

• 2500/1000

• 9/100). Span error is less than 1/5 of the largest error and is therefore insignificant.

FT0202: The zero error is +/-.1% of URL /1000 PSI. Zero error is less than 1/5 of the largest error and is insignificant compared to other errors Span error is +/-.2% of URL per 1000 PSI. Span error is insignificant compared to other errors.

There was no data found to support the accuracy of these flow elements. They are both Orifice type elements, manufactured by Foxboro, and supplied by CE. Per ASME report.

the discharge coefficient tolerance for an orifice will not exceed +/- 1.0% with an appropriately designed and installed configuration. To be conservative, we will assume 42.0% for the FE error.

Charging flow was found to be 41 GPM on several different occasions while running at full power. This works out to -30%h of flow span. Letdown flow was found to be 38 GPM on several different occasions while running at full power. This works out to -25% of flow span. We will assume that these are typical values and calculate the loop uncertainty at these points.

Reference, Comments ref 10 ref 7 ref I ref 7.

ref 19 ref 17.

PPC error Sqrt Root Extrj FIC-0202 error:

Per schematic diagrams, the sense resistors are precision 0.1%. These signals are input through the Cutler-Hammer multiplexor which has an accuracy of 0.04%. As these inaccuracies are less than 1/5 of the largest error, they are insignificant.

As - found tolerance of FY-02 12 is +/-0.8ma over a range of 10 to 50 ma. This works out to

+/- 2.0%. Sqrt extraction is performed internally to FT-0202.

As-Found tolerance of i 2 GPM. This works out to :t 1.3%

ref 12 ref 12 ref 12 FIA-0212 error:

As-Found tolerance of

• 2.8 GPM. This works out to 2%

-oEk UADES NUCLEAR PLANT bu I PMANALYSIS CONTINUATION SHEET mEN U MXMO rsm EA -AFZ - 96 01 Sheet 10 Rev#

2 Reference, Comments Loop Uncertainty for FT0212 @ - 41 GPM Dpp.1 =(Flowpa /10)2

=(30/1 0)2 =9 %DP oput pan Flow Uncertainty

=41o*504-10*/Dp *VFTA,F *FTSP, *FEt,

=10 0*V--l0*/9-V 2+2+22 (worst case)

:L6.470/ fl1owspan Total Logp Flow Uncertainty via PPC PPCLOOPErrr

FU2 +FY2F

=+/-16.47 2

=6.77% = *9.5 GPMa,41 GP ael F

Total Loon Flow Uncertainty via FL4 l~~~~~~

FLA oopEOr = VF AF

+FLU ASF

=6.472+22+22= 17.06% = *9.9 GPM.t41 GpMaelFlew ref 17 ref 17 ref 17 ref 17 Loop Uncertainty for FT0202 @ - 38 GPM Dpp,, =(Flowpa/I 0)2

=(25/1 0)2 =6 2 5%DP ouput span Flow Uncertainty I0* r'p - I0

• VDp *VFTAF *FE,,

I10 -F6.i2 i-I0 V6.C2S -2 PPCIA,,PE,?II, -Flow Uuncertainly=6.S0% = *10 GPM.,3,u Fa Total Lop,, Flow Uncertafnty via FIC FICL OOPEFI

= IFU2 +F2CAF

,6.S02+j32= *6.63%

I11 GPMt 3g PsmactuA Flew

_
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I

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WMANALYSIS CONTINUATION SHEET re, mis

_zmflw a EA -AFZ 01 Sheet 11 Rev#

2 6.8 Letdown Temperature Instrument Uncertainties relative to Heat Balance This is equipment ID TT-0122CD. The range is 515 to 615 F. Per RJ-2 basis, the loop end-to-end calibration as-found is + 1% ( I F). This temperature is a manual input to the PPC heat balance calculation. TSSP RI-2 performs a loop end-to-end calibration of this transmitter.

Reference, Comments ref 9 Meter readability:

This meter has 20F increments. Will assume that the meter is readable to 1/2 of this or +/-

1F.

RTD:

Temp. & P/S effects:

RI-2 uses the specific calibration curve for each individual RTD to check its accuracy.

This eliminates any significant RTD error.

Per RI-2. supply voltage effect is 0.150F. Per RI-2, Ambient temp. effect is tO.003620 F.

Both of these effects are less than 115 of the largest error and are therefore insignificant.

Total Error:

= *ivTemp. LoOPAF tl + Meter.esdbh.

=

12 0 F12

= i: 1.4 F

6.9 Pressurizer Heater instrument uncertainties relat: e to Heat Balance The PPC points are A10103 and AI0104. These are in the same circuit as ammeters EAI-1305 and EAI-1211 respectively.

Circuit

Description:

A Current Transformer (CT) off of the heater breaker feeds a Ammeter and an I/

converter in the control room. The /1 converter in turn is run through a resistor to create a voltage which is input to one of the PPC Multiplexor Nodes. The range of the ammeter, I/l, and the PPC input as a function of engineering units is 0 to 200 amps.

ref 5

s n

§ r n ~~~~~~~:.P

' i aixnr s

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET 371BP h

EA -AFZ -96 01 Sheet 12 Rev#

2 Reference, Comments 9

Instrument Errors:

Current Transformer:

Current to Current Convertor No vendor or accuracy data could be found on this particular CT. However. this a fairly typical type of CT device. Other CTs with the same ratio of 200/5 have an accuracy on the order of 4.8%. There is no calibration associated with this ievice. As this is a passive device, no drift should be expected. To be conservative, this error will be doubled. This works out to 9.6% uncertainty.

This is a Square-D, cat. No CLE-202001, converter. The catalog stated accuracy is 0.25%.

This device is not calibrated. The four converters were calibrated in 1995 under a WO request. To account for the lack of calibration, the catalog stated error will be tripled.

This works out to 0.75% uncertainty. Discrepancies between the channels or between the PPC and meters beyond this should be noticeable by the operators.

ref 5 ref 6 refI 8 ref 21 Meter:

This meter is calibrated per PPAC PCS01 I every two years or Refout. Tolerance is +/-3% full scale.

This meter face is graduated in 20 amp increments. There is a large distance between increments such that the meter can be easily resolved to +/- 5 amps or k2.5%

PPC Accuracy:

Temp. Effect:

The only significant factor for this PPC input accuracy is the sense resistor. Those bought for the CFMS modification were typically 0.025%. The Cutler-Hammer multiplexor is accurate to 0.04% from 20 to 30 C. As these errors are significantly less than 1/5 of the largest error, they are insignificant with respect to this instrument uncertainty.

None. CT has no temp. effect. Other devices are located in the control room.

ref 14, 15 ref 7.

Total Error relative to PPC:

=*

1,12 +CT 2

• 'I/ace c

=/752 +9.62

=9.6am

=

9 amps Total error relative to manual reading:

2

=;CT,c +etre

+Metetrradahhtf

= 19.6" +32+2.52

=

10.36%

=

• 21 amps 6.10 Charging Line Temperature instrument uncertainties relative to Heat Balance Plant Equipment lI1s are TE-0212 / n-0212. This temperature is a manual entry to the Heat balance.

The temperature indicator is calibrated per IPI data-sheet using the impedance curve for a platinum RTD.

Circuit

Description:

A platinum RTD feeds TI-0212 in the Control room. The RTD is a Burns Engineering model 9486.

EA -AFZ 01 IT

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PALISAOE& NUCLEAR PLAN ANALYSIS CONTINUATION SHEEl I Sheet 13 Rev#

2 Reference, I Comments TE-02 12 accuracy:

TI-0212 accuracy:

Burns.atalog information for Platinum RTIDs gives a worst case interchangeability of

+/-3OF at 6000F. As this catalog did not directly address a model 9486. the interchangeability will be doubled and used as the TE error. This works out to +/-60F.

As-found tolerance of +/- 10 F.

ref 20 ref 12 Temperature Effect:

M&TE:

TOTAL ACCURACY:

No ambient temperature effect was noted in the Bums catalog other than a wide operating range limit. The TI is located in control room.

Decade impedance box has accuarcy better than 2 % of reading. This is approximately

!1?% of 600 F range which works out to *0.60F. This is less than 15 of the largest error and is therefore insignificant.

= :k VTE, 2*

TI,2

=

• 62 + t,2

=

12"F ret 20 ref 7

7.0 CONCLUSION

This EA contains instrument uncertainties that are acceptably accurate for input to a heat-balance uncertainty analysis. Where specific vendor accuracy data was unavailable, conservative estimations were made.

MMMM.W.j

ATTACHMENT 3 NUCLEAR MANAGEMENT COMPANY PALISADES NUCLEAR PLANT DOCKET 50-255 October 6, 2003 LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

REFERENCE 9.6: EA-ELEC08-0004, "Uncertainty Calculation for UFM Corrected, Density Compensated Total Feedwater Flow Measurement (PPC Only)," Revision 1 30 Pages Follow

kF.eF6PREVCF-Proc No 9.1 1 Revision 13 Page 1 of I

-ONSUMERS ENERGY PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS COVER SHEET EA-ELECO-0004 Total Number of Sheets Title Uncertainty Calculation for UFM Corrected. Density Comensated. Total Feedwater Flow Measurement PPC Only)

INITIATION AND REVIEW Calculation Status Preliminary Pending Final Superseded 0

x 0

0 Initiated InIt Review Method Technically Rev'r Sup'v Rev Appd Reviewed Appd Description By Aft Detail Qual By S/DR BY Date Calc Rev'w Test By Date Appd

~~~~~~~~RMB 0

Original Issue R.A.

D.M.

Bischoff 3/20102 RMB V

Kennedy 511410 5114102 See Record Of bR4.

1 qS/0-I Revisions Sheet Hamm 7/12102 ?

PALISADES NUCLEAR PLANT EA-ELECO8-0004 ANALYSIS CONTINUATION SHEET Sheet 2 of 30 Revision 1 RECORD OF REVISION Revision Number Description Of Chanae I

The indicated calculation status on the cover sheet has been changed to Pending.

Section 3.5.6, change the minimum calibration temperature to 700F and the maximum temperature to 11 0F.

Changed TETT to 2.52240F.

Added Assumption 4.1.1 to reflect expected plant parameters following the power uprate.

Added Assumption 4.2.7 Changed TETT to 2.52240F Changed TLU Fw to +/-3.6251 IF Changed T1 to 437.07490F Changed D, to 52.1810 1bm/ft3 Changed T2 to 444.3251 F Changed D2 to 51.8424 Changed F1 to 5.6902 Mlb/hr Changed FET to 11.7000 Klbmlhr Changed F2 to 5.6667 Mlbm/hr Changed FET to -11.8000 Klbm/hr Changed FETEMP to +/-11.8000 Klbmlhr Changed TLUFW("SchSG) to +/- 28.6149 Klbm/hr Changed TLUFW to +/- 40.468 Klbm/hr Changed Reference 9.3 to R-24B Rev.0 Changed Reference 9.7 revision to Rev.1 Added Reference 9.17 Rev.0

PALISADES NUCLEAR PLANT EA-ELECO8-0004 ANALYSIS CONTINUATION SHEET Sheet 3 of 30 Revision 1 1.0 OBJECTIVE I SCOPE In order to perform a minor power up-rate, the uncertainties associated with the Secondary Calorimetric computation must be determined. A significant portion of the uncertainties associated with this computation stem from the measurement of Feedwater Flow. In order to reduce these uncertainties, Ultrasonic Flow Measurement (UFM) techniques are used to correct the readings from the Feedwater Flow venturis during full power operation.

This calculation determines the uncertainty associated with the Feedwater Flow measurement used in the secondary calorimetric heat balance calculation, with the UFM correction. This calculation is only intended to be valid for the Feedwater Flow Measurement on the Palisades Plant Computer (PPC) during full power operations after the minor power up-rate. See Section 8.0 for further restrictions on the usage of information from this calculation.

2.0 FUNCTIONAL DESCRIPTION Per Reference 9.2, the Feedwater Flow indication is temperature (density) compensated within the PPC. The instrumentation channels monitor Feedwater Flow to each of the steam generators. Per References 9.2, 9.10 and 9.1 1, the signals are supplied to the Feedwater Regulator System and PPC, as well as to the Control Room for remote indication. Per Reference 9.2, the Feedwater Temperature channels monitor Feedwater Temperature at the E-6A and B outlet to the steam generators. Per References 9.2 and 9.8, this signal is supplied to the PPC and a Control Room recorder.

Per Reference 9.2, "PPC flow indication may be calibration compensated at full power via a correction factor calculated using alternative Ultrasonic Flow Measurement (UFM) technique." This process is addressed in Reference 9.12.

Each steam generator Feedwater Flow signal is density compensated by an associated Feedwater Temperature signal and is UFM Corrected separately.

This calculation only addresses the PPC indication of Feedwater Flow, after temperature (density) compensation and UFM correction.

PALISADES NUCLEAR PLANT EA-ELEC08-0004 ANALYSIS CONTINUATION SHEET Sheet 4 of 30 Revision 1 3.0 ANALYSIS INPUTS 3.1 TEMPERATURE COMPENSATION EQUATIONS Per Reference 9.2, the Feedwater Flow indication in the PPC is temperature (density) compensated. The Feedwater Flow computation is performed by the PPC, and the following equation is used for each steam generator Feedwater Flow signal.

F = G[ + 0.043 (T - 430)]1x60xD 11130

)7.48 Where:

F = Feedwater Flow in lb,/hr G = Feedwater Flow in gal/min T = Feedwater Temperature in 0F D = Density Based on Feedwater Temperature The Feedwater Flow in GPM is obtained from the flow element AP and Feedwater Flow calibration curves. The non-density-compensated Feedwater Flow values, G. for each steam generator is computed in the PPC, as determined in Reference 9.2, as follows.

%INPUIT G = 14.237 x 103GPM 100 3.2 FLOW ELEMENT AND FLUID DENSITY CONSIDERATIONS TAG NUMBER:

FE-0701

[9.2]

FE-0703

[9.2, 9.4.e]

MANUFACTURER:

BADGER METER CO.

[9.4.e]

CALIBRATED BY:

ALDEN LABS

[9.2]

3.2.1 Per Reference 9.12, the UFM correction to the Feedwater Flow measurement is made every 31 days when operating at or above 95%. This correction is performed during full power operation, and this calculation does not apply to low power conditions, or accident conditions. Therefore, this correction negates the effects of fouling on the feedwater venturis, thermal expansion factor of the venturis, and piping configuration effects. Therefore:

ErrorSFE

=rF N/A

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET EA-ELECOB-0004 Sheet 5 of 30 Revision I 3.2.2 Per Reference 9.2, the Feedwater Flow reading is temperature (density) compensated within the PPC. Therefore, the errors due to changes in density are corrected for in the temperature (density) compensation algorithm. The only related residual uncertainty is with respect to the errors in the temperature measurement, which are evaluated in later sections. Therefore, the process effects relating to density changes are negligible.

PE

=

N/A 3.3 FLOW TRANSMITTER CONSIDERATIONS TAG NUMBER:

MANUFACTURER:

MODEL NUMBER:

FT-0701 SPAN:

FT-0703 SPAN:

FT-0701 FT-0703 ROSEMOUNT 3051 CD2 0 - 213.9 "H20 0 - 219.5 H20

[9.2]

[9.21

[9.2]

[9.2]

[9.2]

[9.2]

3.3.1 Per Reference 9.4.a, the Reference Accuracy of the flow transmitter is given as

+/-0.075% Span. Therefore, the flow transmitter Reference Accuracy (RAFT) is given as:

RAFT

=

+/- 0.0750% AP Span 3.3.2 Setting Tolerance effects are errors introduced during the calibration process and are constant at a given point on the calibration curve throughout an operating cycle. The UFM correction to the Feedwater Flow signal in the PPC compensates for any Setting Tolerance effect on the transmitter. Therefore, STF

=

+/- 0% AP Span 3.3.3 Measurement and Test Equipment (MTE) effects are errors introduced during the calibration process and are constant at a given point on the calibration curve throughout an operating cycle. The UFM correction to the Feedwater Flow signal in the PPC compensates for any Measurement and Test Equipment effect on the transmitter. Therefore, MTEFT

=

0% AP Span

PALISADES NUCLEAR PLANT EA-ELEC08-0004 ANALYSIS CONTINUATION SHEET Sheet 6 of 30 Revision 1 3.3.4 Per Reference 9.4.a, the flow transmitter stability term is specified as +/- 0.125%

Upper Range Limit (URL) for 5 years for +/- 500F temperature changes and up to 1000 psi line pressure. This term inherently covers three standard uncertainty terms; drift, temperature effect, and static pressure effect. Sections 3.3.5 and 3.3.7 below specifically address the temperature effect and static pressure effects, but do not address drift. Drift is not specified separately within Reference 9.4.a, so for conservatism, the drift is assigned the full stability value.

Per Reference 9.4.a, the Upper Range Limit for these transmitters is 250 MH2O.

For conservatism, the transmitter with the least span is used. Therefore, the Drift term is established as follows.

DRF

=

+/- 0.125% x (250 "H20 / 213.9 "H20)

=

+/- 0.1461% AP Span 3.3.5 Per Reference 9.4.a, the flow transmitter has specifications for static pressure zero and span effect. The zero term can be calibrated out completely, and the span term can be generally corrected for in the calibration of the transmitter. The residual static pressure span effect is due to the fact that each transmitter responds slightly differently with respect to the span effect, and the correction procedure given merely corrects for the average transmitter response of the all transmitters manufactured. However, in this case, the Feedwater Flow signal is UFM corrected at operating conditions every 31 days, thus correcting these specific transmitters for their static pressure span effect as well. Additionally, since the correction is done at full power operating conditions, only very minor pressure changes need consideration, which have a negligible effect on error.

Therefore, the static pressure effect is negligible.

SPEFT=

N/A 3.3.6 Per Reference 9.4.a, the flow transmitter Power Supply Effect (PSEFT) is given as less than +/-0.005% Span per Volt. Per Reference 9.6, the power supplies for the flow transmitters are regulated to within +/- 5 VDC. Therefore, the flow transmitter Power Supply Effect (PSEFT) is given as:

PSEFT =

+/- (0.005% Span I VDC)(5 VDC)

PSEFT =

+/- 0.0250% AP Span Per Section 7.6.1 of Reference 9.6, random errors less than i 0.05% Span have a negligible impact on the overall uncertainty determination and may be omitted from the loop uncertainty analysis. Therefore, PSEFT =

N/A

PALISADES NUCLEAR PLANT EA-ELECOB-0004 ANALYSIS CONTINUATION SHEET Sheet 7 of 30 Revision 1 3.3.7 Per Reference 9.4.a, the flow transmitter Temperature Effect (TE,) is given as

+/- (0.0125% URL + 0.0625% Span) / 500F. Use of the transmitter with the least calibrated span maximizes this uncertainty term; therefore, the span for FT-0701 is used to compute this term. Per plant walkdown, the transmitters are located in the Containment "air room." Therefore, per Reference 9.6, the required temperature difference to be considered is 601F.

TEFr = +/- (((0.0125%)(250 'H 20 / 213.9 "H20)] + 0.0625% Span](600F/500F)

TEFr

=

0.0925% AP Span 3.4 TEMPERATURE ELEMENT CONSIDERATIONS TAG NUMBER:

TE-0706

[9.2]

TE-0708

[9.2]

MANUFACTURER:

BURNS ENGINEERING, INC.

[9.2, 9.4.b]

TYPE:

200 fQ RTD

[9.2]

3.4.1 Per Reference 9.4.b, the standard accuracy for platinum temperature elements is

+/- 0.10% of Resistance at 0C. This is a bias term for a given RTD. However, since the Feedwater Flow reading is corrected at power operating conditions, this term is negated during the UFM correction process. Also, per Reference 9.4.b, the Repeatability for these RTDs is +/- 0.100F over the range from 320F to 9000F. Per Reference 9.5, the Feedwater Temperature is anticipated to be approximately 438.50F after the power up-rate. Therefore, the Reference Accuracy (RA) of the temperature element is established as its Repeatability.

RATE

=

+/- 0.1000 F 3.4.2 The RTD has no adjustment and therefore cannot be calibrated. Therefore, the errors that can be introduced during calibration (Setting Tolerance and M&TE) do not apply to this device.

STTE

=

N/A MTETE=

N/A 3.4.3 Per Reference 9.4.b, the temperature element has a specification for RTD Interchangeability. At the operating condition of 438.60F, the interchangeability specification is determined from interpolating from the Table in Reference 9.4.b to be as follows:

INTTE =

+/- 2.1925°F

PALISADES NUCLEAR PLANT EA-ELECO8-0004 ANALYSIS CONTINUATION SHEET Sheet 8 of 30 Revision 1 3.4.4 Per Section 10.3 of Reference 9.6, RTD lead wire effects are negligible with 3-wire RTDs. Per Reference 9.8, these are 3-wire RTDs. Therefore, RTD Lead Wire Effects are negligible for this application.

LWTE =

N/A 3.4.5 Per Section 10.4 of Reference 9.6, RTD Self-Heating Effects are generally considered negligible if used with flowing fluids. In addition, since the UFM correction is performed during operating conditions, any Self-Heating errors are removed during the correction process. Therefore, Self-Heating Effects are considered negligible for this application.

SHTE=

N/A 3.5 TEMPERATURE TRANSMITTER CONSIDERATIONS TAG NUMBER:

TT-0706A

[9.2]

TT-0708A

[9.2]

MANUFACTURER:

RIS

[9.2]

MODEL NUMBER:

SC-1374

[9.2]

SPAN:

500OF

[9.2]

3.5.1 Per Reference 9.4.c, the Linearity of the temperature transmitter is given as

+/-0.1% Span, and the Repeatability is shown as +/-0.1% Span. The span of the transmitters is 500OF per Reference 9.2. These two terms are combined to produce the overall temperature transmitter Reference Accuracy (RArr) is given as:

RA-

=

+/- [(0.1% Span)2 + (0.1% Span)J1 1

x (5000F / 100% Span)

RAT

=

+/- 0.7071OF 3.5.2 Per Reference 9.6, the Setting Tolerance (ST) term is set equal to the Final Setting Tolerance for the device. Per Reference 9.3, a loop calibration is performed on the temperature transmitters and the associated PPC points. The setting tolerance on the loop calibration is conservatively assigned as the Setting Tolerance for the Temperature Transmitter, since adjustments are not made to the PPC based on this calibration.

STTT

=

+/- 0.75000F

PALISADES NUCLEAR PLANT EA-ELEC08-0004 ANALYSIS CONTINUATION SHEET Sheet 9 of 30 Revision 1 3.5.3 Per Reference 9.6, Palisades Plant requires that total equivalent accuracy of the test equipment used in the calibration of instrumentation be at least as accurate as the Final Setting Tolerance of the instrument being calibrated. Therefore, the Measurement and Test Equipment effect (MTE) is conservatively set equal to the as-left calibration tolerance of the temperature transmitter. Therefore, per Section 3.5.2 and Reference 9.3, MTET =

+/- 0.75000F 3.5.4 Per Reference 9.4.c, no time dependent drift term is specified for the temperature transmitters. Most frequently, drift for these components is very small in relation to the other uncertainty terms specified. Therefore, the Drift term is considered negligible for the temperature transmitters.

DRTT =

N/A 3.5.5 Per Reference 9.4.c, the temperature transmitter Power Supply Effect (PSET,)

is given as less than +/-0.15% Span per 20% voltage variation. Per Reference 9.8, the instruments are powered by 120 VAC instrument power from YOI. Per Reference 9.6, the power supplies are regulated to within +/- 10%. Therefore, the temperature transmitter Power Supply Effect (PSET) is given as:

PSE 17 =

+/- (0.15% Span / 20%)(10%)(500 F / 100% Span)

PSETT =

+/- 0.37500F 3.5.6 Per Reference 9.4.c, the temperature transmitter Temperature Effect (TETT)

(Zero) is given as +/- [((RTDmin(Q)xO.002%)/span ())

+ 0.008%] / F maximum.

The span effect is defined as +/-0.008% / F maximum. Per plant walkdown, the transmitters are located in the Turbine Building. Per Reference 9.16, the maximum ambient temperature is 10F. Per Reference 9.17, the minimum ambient temperature during a calibration is 700F. Therefore, the required temperature difference to be considered is 400F. Per Reference 9.2, the span is 5000F. Using 0F and 500OF ohm values from Reference 9.15, the temperature effect is computed as follows:

TETn = +/- [(185.88 Q x 0.002% / (398.04 K2 -185.88 Q)) + 0.008%] x (400F) x (5000F / 100% Span)

TETn = +/- 1.95 F TET.s = +/- (0.00008 / F) x (400F) x (5000F)

TETTs = +/- 1.6 F TETT= +/- (TETT2 + TE Tr 2)12 TE,-r = +/- 2.52240F

PALISADES NUCLEAR PLANT EA-ELEC08-0004 ANALYSIS CONTINUATION SHEET Sheet 10 of 30 Revision 1 3.6 PPC INPUT UNCERTAINTIES (FLOW AND TEMPERATURE SIGNAL INPUTS)

For conservatism, the uncertainties of the PPC analog input cards are based on the specifications for the 12-bit AD.

3.6.1 Per Reference 9.4.d, the Linearity of the input A/D card is given as +/-0.04%

Span. The Gain Accuracy is shown to be +/- 0.025% Full Scale. Reference 9.4.d states, "The full scale ranges are user programmable." Therefore, no adjustment must be made to correct the % Span values to the % full-scale values for the inputs. Therefore, the Reference Accuracy of the PPC input cards are computed as follows:

RAppc =

+/- [(0.04% Span)2 + (0.025% Span) 12 1 RAppc =

+/- 0.0472 % Span Per Section 7.6.1 of Reference 9.6, random errors less than +/- 0.05% Span have a negligible impact on the overall uncertainty determination and may be omitted from the loop uncertainty analysis. Therefore, RAppc =

N/A 3.6.2 Per Reference 9.4.d, the PPC input cards should not require adjustment or periodic maintenance. Setting Tolerance effects are errors introduced during the calibration process only. If adjustment is required for the input cards, high precision equipment are used with extremely tight tolerances to ensure that very accurate readings are obtained. Therefore, the effects of Setting Tolerance and Measurement & Test Equipment are negligible with respect to the other uncertainty terms.

STPPC

=

N/A MTEppC

=

N/A 3.6.3 Per Reference 9.4.d, no drift is specified for the PPC cards. As stated therein, periodic maintenance should not be required for the input cards. Therefore, drift is negligible with respect to the other uncertainty terms.

DRppc =

N/A

PALISADES NUCLEAR PLANT EA-ELECO8-0004 ANALYSIS CONTINUATION SHEET Sheet 11 of 30 Revision 1 3.6.4 Per Reference 9.4.d, the PPC input card gain stability is shown to be

+/-1 OOppm/OC and the zero stability is shown as +/-0.5jiV I1'C for the Gate card and

+/-45jiV / C for the A/D card. This is a temperature effect (TEppc) specification. (A 1.25 VDC full-scale value is used for conservatism). The plant computer inputs are located in an environment similar to that in the control room. Therefore, per Reference 9.6, the temperature difference for consideration is 150F. Therefore, the temperature effect is converted to correct units and combined to determine the following total Temperature Effect expression:

TESPEC =

i [(100/1,000,000)2 + (((0.5)2 + (45)2)112 x I-4/ 1.25)121 x1 000%/C TEppc =

+/- 0.010628% Span / C x [1 C/1.8 0F1 x [1 50F]

TEpp

=

+/- 0.0886% Span TEPPCF=

+/- 0.0886% Span TEPPCT =

+/- 0.0886 x 500OF / 100% Span TEPPcT =

+/- 0.44280F 3.6.5 Per Reference 9.4.d, the quantizing error for the PPC input card is given as +/- t/2 LSB. This term is treated as Resolution (RES). Conservatively using a 12-bit A/D card, the value is computed in terms of % Span as follows:

RESPPc

=

+/- 0.5 x [1/(2)11 x 100% Span

=

+/- 0.0122% Span Per Section 7.6.1 of Reference 9.6, random errors less than +/- 0.05% Span have a negligible impact on the overall uncertainty determination and may be omitted from the loop uncertainty analysis. Therefore, RESppC

=

N/A 3.6.6 The UFMs are used within Reference 9.12 to correct the Feedwater Flow (venturi) reading to equate to the UFM reading. This requires that the Correction Factor be computed manually. Per Reference 9.12, the display resolutions of the UFM value and the PPC flow values are equivalent to 5 and 6 decimal places for MPPH indications, respectively. Using 2 the least significant digit as the resolution of these terms, the resolutions are 0.5 and 5 bmlhr, respectively.

Therefore, combining these terms into a Correction Factor (CF) Resolution, REScF=

+ ((0.5 lb,/hr)2 + (5 Ib,/hr)2)" 2

=

+/- 5.025 Ibm/hr This equates to approximately 0.0001 % Span, which is negligible per Section 7.6.1 of Reference 9.12 (i.e. <0.05% Span).

PALISADES NUCLEAR PLANT EA-ELECO8-0004 ANALYSIS CONTINUATION SHEET Sheet 12 of 30 Revision 3.7 ULTRASONIC FLOW METER (UFM) UNCERTAINTY CONSIDERATIONS 3.7.1 Per Section 4.3.1 of Reference 9.7, the UFM uncertainty (,.) is established as

+/-0.4445%. Per Assumption 4.2.2, this uncertainty value is assumed to be valid after power up-rate. Therefore, e,,

=

+/- 0.4445 % Actual Flow 4.0 ASSUMPTIONS 4.1 MAJOR ASSUMPTIONS 4.1.1 Per Reference 9.5, the following plant parameters are anticipated after the power up-rate project. If actual plant conditions are similar to these, this calculation remains valid.

PSG =

Steam Generator Pressure (psia)

PSG =

765.8 psia Tm- =

Feedwater Temperature (F)

TF-W =

440.70F FFW =

Feedwater Flow (Mlbm / hr)

FFw =

11.357 Mlbm / hr 4.2 MINOR ASSUMPTIONS 4.2.1 Per Reference 9.7, the PPC updates Feedwater Flow readings once per second.

A rolling average of these one second snapshots is used to filter the values.

The hour averages are composed of ten minute averages which are composed of snapshots taken at a one minute interval. Each level requires 90% of the points being averaged to be valid. The rate of sampling is appropriate for the determination of a valid Feedwater Flow signal.

4.2.2 The error introduced into the measurement of Feedwater Flow due to the numerical development of a square root and other computations within the PPC is negligible with respect to the other error terms. The internal resolution of the PPC Feedwater Flow value is adequate to impart a negligible overall effect on the secondary calorimetric computation.

PALISADES NUCLEAR PLANT EA-ELECO8"0004 ANALYSIS CONTINUATION SHEET Sheet 13 of 30 Revision 1 4.2.3 Differences in Feedwater density determined by the PPC and Feedwater density from ASME Steam Tables are a minor bias that is nullified each month when the UFM correction is made. The temperature remains relatively constant from month to month, so any induced uncertainty is negligible.

4.2.4 Per Reference 9.7, all uncertainties associated with the Ultrasonic Flow Meter (UFM) are random and independent. No bias uncertainties are present in the ultrasonic Feedwater Flow measurement.

4.2.5 The uncertainties derived per Reference 9.7 for the UFM measurement apply at the full power and full Feedwater Flow values used after this power up-rate.

4.2.6 Per Reference 9.12, density correction is performed for the UFM measurement, when determining the correction factor to use in the PPC. Reference 9.7 derives an overall uncertainty value for the UFM measurement. This derivation includes a density uncertainty factor, but gives no specific details as to the origin of that term. The uncertainty computation for the UFM measurement within Reference 9.7 properly considers the density correction process as applied in Attachment 2 of Reference 9.12, Steps D and J.

4.2.7 RI-24, Steam Generator Feedwater Flow Instrument Loop Calibration,"

Procedure, has been revised to remove the calibration of the feedwater temperature channels. A new procedure, RI-24A was created for the temperature channel calibrations. This will ensure the transmitters are calibrated with an ambient temperature of 700F or greater.

5.0 ANALYSIS Computations are performed to an accuracy of several significant digits, but presented in this calculation rounded to four decimal places in most cases.

Hand verification of this calculation utilizing the rounded values yields slightly different results, due to round off errors. The final result is rounded to three decimal places for use as input to the Secondary Calorimetric uncertainty calculation.

This analysis is performed in two segments. The first segment assesses the potential error of the Feedwater Temperature, as measured in the PPC, and determines the affect of this error on the flow reading. The second segment then combines the errors of the Feedwater Flow measurement with any required errors from the Feedwater Temperature and UFM Correction, to determine a final uncertainty of the Feedwater Flow value in the PPC, with UFM correction applied.

PALISADES NUCLEAR PLANT EA-ELECOB-0004 ANALYSIS CONTINUATION SHEET Sheet 14 of 30 Revision 1 5.1 FEEDWATER TEMPERATURE UNCERTAINTY ANALYSIS Per Analysis Input Sections 3.4, 3.5, and 3.6, the following non-zero values are derived, which require uncertainty consideration for the Feedwater Temperature measurement within the PPC.

RATE

+/- 0.1000 F

[3.4.1]

INTTE=

+/- 2.19250F

[3.4.3]

RAr

=

+/- 0.7071cF

[3.5.1]

STTT

=

+/- 0.75000F

[3.5.2]

MTETT =

+/- 0.75000F

[3.5.3]

PSETI. =

+/- 0.37500 F

[3.5.5]

TETT

=

+/- 2.52240F

[3.5.6]

TEppcT=

+/- 0.44280F

[3.6.4]

All of the above errors are random and independent, and expressed in common units. Therefore, in order to determine the uncertainties of the plant computer indication of Feedwater Temperature, with respect to the computation of UFM Corrected Feedwater Flow, the terms are combined by SRSS.

TLUFWT =

+/- [RATE2 + INTTE2 + RArr + STTT2 + MTETT2 + PSETT2 + TETT2

+ TEppc-rj1' TLUFWT =

+/- 3.6251 F In order to evaluate these errors in terms of their affect on the flow measurement, a case study is performed at the anticipated flow rates during normal operation after the power up-rate. Given ideal inputs, the flow equation in the Plant Computer is implemented. Then, errors are applied to the temperature inputs, and a difference in flow measurements is observed, holding all other values constant.

Per Section 3.1, the following is the PPC equation used to perform the temperature compensation for the Feedwater Flow instrumentation:

F = G + 004(T T-430)] I x60xD E

130 7'j

.48 Per Reference 9.5, the Main Feedwater Flow anticipated at 101.4% power, after power up-rate, is 11.357 Mlb,/hr. Splitting this between the two steam generators equally, we obtain Feedwater Flows for each steam generator of:

FINrT = FTOTAL / 2 = 11.357/2 = 5.6785 Mlb,/hr

PALISADES NUCLEAR PLANT EA-ELECO8-0004 ANALYSIS CONTINUATION SHEET Sheet 15 of 30 Revision I Also per Reference 9.5, the main Feedwater Temperature anticipated at 101.4%

power, after power up-rate, is 438.50F.

TINrr

=

440.7-F Per Reference 9.13, a pressure of 700 psia was used in obtaining the densities since this pressure is close to the 100% power value and density is not highly dependent on pressure. Density is calculated using the following equation per Reference 9.13:

D =

61.2257 - (0.0000585417)(T2)) + (0.00489334)(T)

Thus, DINrr

=

52.01243 lba/ft3 Therefore, the equations are worked as follows to determine the ideal measured flow rate.

GINrI

=

FINrr / ([1 +(0.043/130)(TINrr 43 0)] x [60DINIT7.48J}

GINI

=

13,562.59 GPM The only parameters in the Flow equation that change are T, the measured Feedwater Temperature, and D, the density from the PPC computation, based on the measured Feedwater Temperature. The total loop uncertainty for the temperature reading on the PPC is established as +/-3.6251 OF for the evaluation.

In order to account for any errors in the density algorithm of the PPC, the densities from the erroneous temperatures are computed with the PPC algorithm, to specifically acquire what the PPC would compute for these items.

Per Reference 9.13, the density equation in the PPC is as follows:

D =

61.2257 - (0.0000585417)(T2)) + (0.00489334)(T)

Where:

T = PPC input temperature of TT-0706A or TT-0708A D = Feedwater Density The temperature and density figures (as would be derived in the PPC) for this assessment are as follows:

Case 1:

T.

=

437.0749OF Di

=

61.2257 - (0.0000585417)(T 12)) + (0.00489334)(T)

D1

=

52.1810 Ib,,`l3

PALISADES NUCLEAR PLANT EA-ELECO80004 ANALYSIS CONTINUATION SHEET Sheet 16 of 30 Revision I Case 2:

T2

=

444.3251 F D2

=

61.2257 - (0.0000585417)(T22)) + (0.00489334)(T 2)

D2

=

51.8424 Ibm 3 From Section 3.1, F=G + 0 043 (T-4303 I x60 xD 130

'] 7.48 Substituting the values for Case into the flow equation yields the following erroneous flow reading (F).

F.

=

5.6902 Mlbm/hr Thus, the temperature induced flow error (FET+) is shown for Case I as follows:

FET

=

F1 -

FINIT FET

=

+11.7000 Klbm/hr Substituting the values for Case 2 into the flow equation yields the following erroneous flow reading (F2).

F2

=

5.6667 Mlbm/hr Thus, the temperature induced flow error (FET) is shown for Case 2 as follows:

FET

=

F 2-FINIT FET

=

-11.8000 Klbm/hr Although the error is slightly skewed in the negative direction, the errors did originate from random errors with equal positive and negative magnitudes. For conservatism, the errors are treated as equal in each direction, with the largest magnitude in both directions.

FETEMP

+/-

+/- 11.8000 Klbm/hr

PALISADES NUCLEAR PLANT EA-ELECO8-0004 ANALYSIS CONTINUATION SHEET Sheet 17 of 30 Revision 1 5.2 FLOW INSTRUMENTATION UNCERTAINTY ANALYSIS Per Analysis Input Sections 3.2, 3.3, and 3.6, the following non-zero values are derived, which require uncertainty consideration for the Feedwater Flow differential pressure measurement within the PPC.

RAT =

+/- 0.0750% AP Span

[3.3.1]

DRF

=

+/- 0.1461% AP Span

[3.3.4]

TEFT =

+/- 0.0925% AP Span

[3.3.7]

TEppc =

+/- 0.0886% AP Span

[3.6.4]

All of the above errors are random and independent, and expressed in common units. Therefore, in order to determine the uncertainties of the plant computer indication of Feedwater Flow (in percent of AP Span), with respect to the computation of UFM Corrected Feedwater Flow, the terms are combined by SRSS.

LUFwDp

[RAW DRT2 + TET2+ TEppcFj

=

+/- 0.2083% AP Span

=

+/- 0.002083 of AP Span Per Reference 9.1, these errors are converted to units of flow as follows:

C = A"2, and eC(SRSS)

+/- eA(R) / 2(A)12 Where:

A is the normalized input differential pressure value, expressed as a fraction of the input span.

C is the normalized output signal in terms of fraction of Flow Span.

ec is the error of the flow signal (% Flow Span) eA is the error of the differential pressure signal (% AP Span)

LUFw =

+/- LUFmp / 2(A)1'2 This analysis is performed only at full power conditions after power up-rate. Per Section 5.1 above, the Feedwater Flow rate of concern is:

GINr

=

+/- 13,562.59 GPM

[5.1]

PALISADES NUCLEAR PLANT EA-ELECOB-0004 ANALYSIS CONTINUATION SHEET Sheet 18 of 30 Revision I Per Section 3.1, G=14.237 1

x103GPM 71100 In this equation, A is equal to the %INPUT term expressed as a fraction.

A

=

%INPUT/100

=

[GINrr / (14.237x103)] 2 A

=

0.9075 The resulting equation from Reference 9.1 expresses the result in terms of

% Flow Span. In order to express the error in process units, the equation is adjusted. The equation is divided by the normalized flow rate, C (which equals A12), to obtain units of % Actual Flow, and then multiplied by the actual flow to obtain process units.

LUFw =

+/- [(LUFwDP /2 (A)"2) / (A)'J x (FINn.)

LUF

=

+/- (LUFWDP / 2A) x (FINIT)

LUF

=

+/- [0.002083 / (2 x (0.9075))] x (5,678,500)

LUFw =

+/- 6.5170 Klbm/hr This is the total loop uncertainty of the differential pressure loop input to the corrected Feedwater Flow computation, expressed in terms of process units.

5.3 TOTAL UNCERTAINTY COMPUTATION FOR UFM CORRECTED FEEDWATER FLOW MEASUREMENT In order to develop the uncertainty of the total measurement of Feedwater Flow, using the UFM correction, one must combine the errors of the different inputs.

The errors for each of the components are combined for each flow loop, and then combined to obtain a total Feedwater Flow measurement uncertainty.

There is a separate UFM correction factor applied to each flow loop, with an associated uncertainty as shown in Analysis Input 3.7.1.

=

+/- 0.4445% Actual Flow

[3.7.1]

so

+/- 0.004445 Actual Flow This is converted to process units as follows:

EGp

+/- 6,* FINIT

£,,p

+/-

+/- 0.004445

• 5678500 Klb,/hr

£+p

=

+/- 25.2409 Klb,,/hr

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET EA-ELEC08-0004 Sheet 19 of 30 RevisIon I Each of the three errors below can now be combined in process units to determine the error for the Feedwater Flow measurement for each steam generator.

E.p

=

+/- 25.2409 Klb1Jhr LUFw

=

+/- 6.5170 Klb,/hr FETEMp =

+/- 11.8000 Klbr/hr TLUFw(EachsG) =

+/- [p2+ LUFW2 + FETEMPJ1]2 TLUFW(Each SG) =

+/- [(25.2409)2 + (6.5170)2 + C11.8000)112 TLUFw(E,.hsG) =

+/- 28.6149 Klb,/hr I

Total uncertainty of the Feedwater Flow measurement with UFM correction is figured by combining the flow errors from each SG in SRSS fashion. This is shown as follows:

TLUFW TLUFw TLUFw

=

i TLUFW(E SG) + TLUFW(E SG) 2

=

+/- [28.6149)2+ (28.6149)112

+/- 40.468 Klbm/hr I

6.0 SETPOINT EVALUATION No setpoints are addressed by this calculation.

7.0

SUMMARY

OF RESULTS The instrument uncertainty of the total Feedwater Flow measurement within the PPC, with temperature compensation based on Feedwater Temperature, and Ultrasonic Flow Meter Correction every 31 days, is determined to be:

TLUFW

=LF

+/- 40.468 Klbm/hr

PALISADES NUCLEAR PLANT EA-ELEC08-0004 ANALYSIS CONTINUATION SHEET Sheet 20 of 30 Revision I

8.0 CONCLUSION

The total loop uncertainty shown in Section 7.0 above can be used in the determination of uncertainties for the Secondary Calorimetric computation.

The intermediate values within the calculation are NOT valid for use independently for other applications, as these are developed only as they apply to a corrected FW flow measurement in the PPC. Therefore, many terms that are compensated for in the FW flow measurement (and are therefore eliminated from this calculation) actually exist in the measurement when used for other purposes.

This calculation is only valid at full power operation after the associated power up-rate. It is not valid at significantly lesser flow rates or power levels. These uncertainty values only apply to the PPC Feedwater Flow measurement in the PPC. They do not apply to situations where other indicating devices are used to determine temperature and flow rate.

PALISADES NUCLEAR PLANT EA-ELEC08-0004 ANALYSIS CONTINUATION SHEET Sheet 21 of 30 Revislon I

9.0 REFERENCES

9.1 ISA-RP67.04, Part II - 1994, "Methodologies for the Determination of Setpoints for Nuclear Safety Related Instrumentation," May 1995.

9.2 RI-24, "Steam Generator Feedwater Flow and Temperature Instrument Loop Calibration," Basis Document, Revision 9.

9.3 RI-24B, "Steam Generator Feedwater Flow Instrument Loop Calibration,'

Procedure, Revision 0.

9.4 Vendor Manuals

a. Flow Transmitter Rosemount Product Data Sheet 00813-0100-4001, "Model 3051 Transmitter," (Excerpts Included as Attachment B).

b. Temperature Elements: M206 Sheet 115, Bums Engineering Inc. Product Specification Bulletin for Resistance Thermometers for All Environments," VTD-0622-006, Revision 3.

c. Temperature Transmitters: RIS / Ametek Signal Conditioning Spec Sheet (Excerpts Included as Attachment A).

d. PPC Analog Input Cards: M0001 PA Sheet 1557, "Computer Products Technical Manual for RTP7436 Series Universal Analog Input Card Set," VTD-2016-0008.

e. Flow Element: M252 Sheet 0032, "Alden Research Laboratories Calibration of Two 16.500" Lo-Loss Tubes," VTD-1 154-0002.

9.5 EA-RCH-01-05, "Calculation of Chapter 14 Safety Analysis Parameter Changes Due to FC-977 Power Uprate," Revision 0.

9.6 EGAD-ELEC-08, "Instrument Loop Uncertainty and Setpoint Methodology,'

Revision 0.

9.7 EA-UFM-97-01, Feedwater Flow Uncertainty with UFM Correction Factor,"

Revision 1.

9.8 Drawing E-76, Sheet 7, "Schematic Diagram, Feedwater and Turbine Driver Instrumentation," Revision 17.

9.9 ASME Steam Tables, 1967, 5t1 Edition.

9.10 Drawing E-69, Sheet 1, "Schematic Diagram, Feedwater Flow Control Instrumentation," Revision 31.

PALISADES NUCLEAR PLANT EA-ELEC08-0004 ANALYSIS CONTINUATION SHEET Sheet 22 of 30 Revision I 9.11 Drawing E-69, Sheet 1A, Schematic Diagram, Feedwater Flow Control Instrumentation," Revision 5.

9.12 MT-15, "UFM Data Collection, Analysis, and Implementation," Revision 1.

9.13 EA-FC-933-05-01, "SPI System Replacement," Revision 1.

9.14 Deleted 9.15 Instrument Calibration Sheets for TT-0706A and TT-0708A, dated 12/13/01 9.16 Palisades Nuclear Plant Final Safety Analysis Report Chapter 9, Table 9-13 Revision 23, "Design Basis Ambient Conditions".

9.17 RI-24A, 'Steam Generator Feedwater Temperature Instrument Loop Calibration," Procedure, Revision 0.

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET -ATTACHMENT A EA-ELECU-80004 Sheet 23 of 30 Revision I RTD and SlIdewire Trarnsmitter SC-130OR

• Sridewlre Inputs

• High output toad option SC-1372, SC-1374

• RTD Inputs

• Optional Input/output Isolation

• Differential RTD inputs

• High output load option SO-1300R, G-1372, and SC-1374 The SC-1300R acoepts a drct potentiometer Inpt and cverts t o a current or vlag ulW.

The Sr-1372 ccepts an pt ro an RTD and cOnverts o a sffrt or voltage alyl. The SC1372 accepts two or tee-wire RT(s witM bted wir conpnistim D mteeralas RID measuremnt Is efbbe. This t s isolated between toIe hput output and power or AC or isted DC powered us The SC-1374 Is simlar to the SC-1372 but Is not Isted tween the qut and power or AC powered uns sC-1372 and SC-1S74 Specifications Inputs: 1000 platursn. tn copper and 120Q nidl. standar Conut factory for other available ares. I to 12EO spans with differenUtal es-Ambient Temperature Effect For 25F to 125F -41C to 52C):

R10xq X0XM2+ 000%t'f n Spar 008%11fmaxkv~r0 For 10nspenwith 1 RTDIninum 0.028%/P zero dtt 0.008%1'F span dift nmemn Response lme:

SC 1372: ess than 400 mS (10-90%)

SC-1374: tessthan60mS0119 lotion:

S0-1372: 00 VAC or 1000 VOC Ipuoutpu/power for AC or isolated DC powered units.

SC -374:

MVAC or 000 VC irtpAwer rAC or oated DC powered wits.

SC-11300R Specifications hxn t0t2 to 20,0000 spen. Totd lre ancme n be speled wen ora Sde PW Dissatsn tess than 175 nricrws Sidewir. Constant Crent Source:

Sttdewre Rane' Slldewr CunwR Mbh max Maximum 0-100 0-8C to A 0-600 oSt 0nIA 0-10M 01090M 10 A 0-2000 0-39oK0 6MA 04 0-7900 2 A 0.500 0-1490C 1 mA 0-1500 0-29990 0.5 A 030000 0-594 025 A 0-84990 0-10.0000 0.150WA

'Totl dWre esistance nO be WOWd hn less ml 0 mr~sech (10-0%)

tolator 600 VACor 1000 VDC bVUL0ower IoSltin fr AC or isolated CC powered Ambient Tempenture Effect for 25-to 125'F (-4 to i(101%fF (:1:0.018%W' ina*TM

.004%oF 4l+/-O.07'Q il 7.43 1

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET - ATTACHMENT A EA-ELECMY80004 Shoot~~~~~~~~~~~~~

~~~~~~~~~~

')A If VIft

-a

-I,--, -- --
V WVV1Q)3W II AMETEK Signal Conditioning SC-1300R, 5C-1372, and S-1374 SpecIfications Uneaft 0.1% of apen, fredmat ww. *1*1 max. 1o 14 and Pt Ris.

0.30C typical fepeatabliy 0.1% de, mmxfm nwor Amnent Temperature Range:

0 to 140-F (18' to 6O-Output Signfs mA Out Druve Capability 1050 mA 3200 440 mA a

02-1 mA Ism=

VDC Oupt Impance 2.10VOC 50M 0.2-1 VWC 50 0-iCO mVDC 50 0.t0asJC 0.50 Any of tw above mwes can be zero baed Lead Camvensation E1ror.

iLeadt Ristance a x 1 mdun

-SS~~~1 Flkiu This eor may be mllted by ero 81Ugnet.

Controls: fllsiturnzro and am Ct oflt Common Mod Rejection (SC-17 130 dBi 0 eo H Power Supply Ettect 0.15% br

+/-20% power veation xkmmi wfth 800 c*in ba and 4-20 mA eutput t3. M. H5options *10%)

Power Supplies:

a. 115VAC20t

.(

H,5watts

b. 24 VOC *20% 3.5 watts (Hi suffbt nonalet C. 230 VAC120%, W H80A 5 was

d. 18VACZ1M0% H.waftts"3 salk:;P-11 rA-t2oplor

.t 15 VAC1O6%, 50/0H2, 5 wats

-4 uftl: P-i11 r A-12 ton) 2 VAC10%, 5tOHzW, 5wats lsuffix: P-I or A-12 option)

. 24 VOC +/-20%, 4.5 watts e uok Ih 48 VDC *20%. 5 watts, 1 sufix Net Weight (Approxinate:

3.4 M. (1 4 t

Enclosures:

Single Uti SIAfce mount tndari

b. P-11. high density, 19'reckmta (with rear access tmi bbdg)

c. A-12, hh density, 19 rackrld suface mrowt (with ton access

d. NEMA 4 mnd 12I rmceaoD24 MN 0- exPloelon-rootsingle u*,.FM approaed for am 1. EPflsln 1, Groups C and 0 Hig Load Drive Option (HO):

MA output 01111" Capability 10-80 M 03 4-20 eM10 2-10 m 2

1-Ge 8403 Nota: NVr-kg outpt May also be zeobased True Voltage Output Optio (Vq:

VOC Mffinimum Dnlv.

imPedance 0-1OVOC 830 0-OvitC 130 Agency Approrvats-FM appronedlo ordinry locaton and hamdou iI-1-OsosI and2 Z lss 1.

• -Mv C & D. alss II, GrcsupsE. F &.

Ametek esc10-PrOci housin read CrA poed fo,ay locatins. al u*it temWM ar 11 7 VAC 24 NMC lsolate or 24 hOC ral-Isofet poeaa Ordering tnmatlon sea page 7.5e, 7.87 Dimensions:

see page 7.8 SC-1300R Connections SC-1372 and S-1374 ConnectIons at.-LR INPUT.

M ABFR AC. --

CC FOR TVV0*WPE MD AC f-OROC V

THRE WIRE C olttere ntllput mConceee C0-1=7 50-1874 r5

} R C"

7.44 I....

.-...-.1 m -.

PALISADES NUCLEAR PLANT EA-ELEC08-0004 ANALYSIS CONTINUATION SHEET - ATTACHMENT B Sheet 25 of 30 Revision I Product Data Sheet 00813-0100-4001 I@lod'ef 3051 Transmitte For Flow, Level, and Pressure Measurement PERFORMANCE o.8

• Industryi best total perrmance of 0.1SX maximizes loop perormance

- Five year stabily of 0. 125% dramatically reduces calibration and maintenance costs

- Faster dynamic response pefrmance reduces process variabilIty

• 100:1 Rangeablity reduces Inventory costs COMPLETE POINT SOLUTIONSO

• Compact, lightweight Coplanar design Fi optimizes performance and minimizes on-site Inventory requirements.

• Integral mount mannfoldMooel 3a14u0 can

,~.-

save over 20% on installation costs by allowing Rosemount Inc to nsta1, lak check, and calibrate the transmnitter/

PATHWAY TO THE FUTURE manifold system.

• Plantweb architecture enabled with

• Model 1199 tuneddirectmountdiaphragm HART' orFouNoATMoNr

heldous, seals can save over20% on procurement Increases access to field Information to and installation costs, while Improvtng improve plant perkrnance performance and response time over 10%.

• Asset Management Solutions (AMS) plant

• Integral mount Annubar flow element can management software cuts costs by save over 50% on installation costs by streamlining maintenance tasks allowing Rosemount Inc. to assemble, leak

• Provides a platform for advanced check, and calibrate the flow meter system, diagnostics and control anywhere' and by reducing pipe penetratlr

• Continuous design Improvement assures

• Direct mount Hookups system for fow and superior performance and savings level Instaffatfion can reduce purchasing specification and Installation ost 30%, and reduce maintenance over 20%.

The World's Best Transmitter Keeps Getting Better...

• Total Perfonnance Improved2X

• Stability Improved 1.5X ROSEMOUNT

%A mm BUS3DUxrMm*ITk ?NSkt1W

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET - ATTACHMENT B EA-ELECOB-0004 Sheet 26 of 30 Revision I Model 3051 Transmitter for Flow, Level, and Pressure Measurement The Model 3051: Superior Performance A TRADmON OF EXCELLENCE With the Introduction of the Model 1151 Pressure Transmitter n 1969, Rosemount Inc. established itself as the industry leader in transmitter technology. The Model 1151 transmitter introduced revolutionary process control technology with the capacitance sensor, a new and highly accurate method of measuring pressure.

Rosemount Inc. Invented HART communication protocol, which Is used In over 70% of smart field devices. Carrying this tradition into the 1990s and beyond, Rosemount Inc. continues to offer improved performance, economical upgrades. and advanced diagnostic systems (such as AMS Performance software), and Rosemount Inc. is the first in the process control industry to insal FouNDroN fieldbus networks.

THE MODEL 3051 TRANSMITTER:

CARRYING ON THE TRADITION With the introduction of the Model 8051 transmitter in 1988, Rosemount Inc. continued its tradition of excellence. The Model 3051 transmitter established a new standard of performance. With its patented CoplanarXlatform and Rosemount Complete Point Solutions package, the Model 3051 transmitter offers the most advanced measurement capabilities available. Today, the Model 3051 transmitter Is the world's most popular flow, level, and pressure transmitter with over one million sold. The key to Its unparalleled success Bes in the ability of Rosemount Inc. to consistently meet and exceed customer needs in performance, value. and continuous improvement.

Value The Model 8051 transmitter yields a high return on investment in several ways:

Five year stabillty without calibration reduces maintenance costs by approximately

$140.00 per point per year Total Performance o 0.15%

reduces process variability and manufacturing coats and can increase profitability up to 30%.

Rosemount Complete Point Solutions provides complete factory-calibrated, pressure.

tested, configured measurement systems right out of the box. Just install, and the Model 3051 transmitter is ready to go to work for you.

The Coplanar Platform reduces parts costs and spares inventory by reducing the total number of parts needed for installation and operations. Versatility is inherent in the Model 3061 Coplanar platform design. Customers choose the sensor module, process connection, remote seal, and primary element that beet fit their need, assuring Complete Point Solutions every time.

Compatibility with advanced diagnostic tools such as Plantweb field architecture, AMS software, and FbUNDAION-fOeldbus provide additional paths to process control, increased uptime, and increased profitability.

Continuous Improvement: An Investment In the Future Upgradeable technology and continuous design improvement assures that the Model 3051 transmitter is ready to work for you now *nd in the future.

9 2

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET - ATTACHMENT B EA-ELEC08-0004 Sheet 27 of 30 Revision I Rosemount Inc.

Specifications PERFORMANCE SPECIFICATIONS Tolt Pevosi M.Ce helsed on eyned rrs d fmereec asufcy amhent tpostpn o edec.ands sttic poessore etm.

Fioetefdpetrance Vaprxocaions see pae IS Reference Accuracy t0.075% of span.

Total Performance 9P e

+0.15% of span for +/-50 F (28 C) temperature changes, up to 1000 psi (6,9 MPa) line pressure (CD only), from 1:1 to 5:1 rangedown.

Stability 1"'Ploved

0.125% of URL for 5 years for +/-50 F (28 C) temperature changes, and up to 1000 psi (6,9 MPa) line pressure.

Dynamic Performance Total Response Time (Td + Tc) 100 ms Reference Accuracy

+/-0.10% of span.

Stability

+/-0.2% of URL for 1 year.

Reference Accuracy

+/-0.05% of span.

Total Performance Imirovedi

+/-0.1% of span for +/-50 °F (28 C) temperature changes, up to 1000 psi (6,9 MPa) line pressure, from 1:1 to 5:1 rangedown.

Stability P,°4ed

+/-0.125% of URL for 5 years for +/-50 F (28 C) temperature changes, and up to 1000 psi (6,9 MPa) line pressure.

Dynamic Performance Total Response Time (Td + Tc) 100 ms Reference Accuracy

+/-0.075% of span.

Reference Accuracy

+/-0.075% of span.

Stability

+/-0.1% of URL for 12 months for Ranges 2 and 3.

+0.2% of URL for 12 months for Ranges 4 and 5.

Rosemount Conformance to Specifications When you buye Rosemount eansnitter you c be oeenf you are 5ettieg a Lower upper ransmiter that ot onty meets. bul most likely grouy euceeds.

te published Specification Specif ton Opelicuon Our aduraned manuficlurng e-hniqueS and inplerwnantiuon of Limit Limit stastical proess cuntro proeidre spesahcauion roomrance o.t least 3041).

Our onemeitenen to coetinualtm hve est enrures that pnoduct

design, retiabdly and Wertormance get bettr every year. By torusing on our enutactanigI sroess. we are able to reduce product voriubity and ou speO'icions have ipned accordingly.

The Model 30t h bensrte, speuications have npeend euery year since inbodudion in i Ll Whle most o these changes do not ate ai out rrad apearance aS od the changes Invease the setaeofeach Model 3051 hensr.tre shipped.

The transines that Rosemewnt Inc. ships tomoso iU be even bettr tme unats shipped tuoy. The r-osul you.lw-y. get the best possible transoitete rote Rosao t

oint

' -- 200rt 19--

99fi8 yti Sigtoe) tePa hsuircanynbot as cesioare the sutdrddeeuto th e noeaa oulue of a norrnnu/dusoueo.

9 13

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET - ATTACHMENT B EA-ELECO8-0004 Sheet 28 of 30 Revislon 1 Model 3051 Transmitter for Flow, Level, and Pressure Measurement DETAILED PERFORMANCE SPECIFICATIONS Reference Accuracy 3051 CD Ranges 2-5 and 3051CG

+/-0.075% of span For spans lew than 10:1, accuracy 002 +0.00 6(URL% dapan 3051CD Range I

• 0.10% ofspan.

For spans less than 15:1, accuracy 4025. + o.o0(SU)RLj of span 3051CD Range 0

+/-0.10% of span.

For spans less than 2:1 accuracy

• 0.05% ofURL.

3O51TICA Ranges 1-6

• 0.075% ofspan.

For spansless than 10:1, accuracy-40.007()]% e8pan 3051CA Range °

+/-0.075% ofspan.

For spans less than 5:1, accuracy-1o[025 +.01URML)]% efSpan S051HI3051L

+/-0.075% of span. For spans les then 101.

accuracy.

40. 026 o+ O(0!R+/-)]L of pan 3051P

• 0.05% of span.

Ambient Temperature Effect per 50 F (28 C) 3051CD0CG

• (0.0125% URL + 0.0625% span) from 1:1 to 5:1

• (0.025% URL + 0.125% span) from 5:1 to 100;1 14 Range 0 t(0.25% URL + 0.05% epan)

Range 1: *(0.1% URL + 025% spen) 3051P

• (0.006% URL + 003% span) 30s1H

• (0.025% URL + 0125% span + 0.35 inH20)

For spans below 801 rangedowE

• (0.035% URL + 0125% pan + 0.35 In 2O) 3051L See the Rosemount Instrument T-11det or SOAP 2000 oft-am 3O51T and 3SCA

• (0.025% URL + 0.125% pan) from L1 to 30:1

• (o.0os% URL + 0125% span) from 80:1 to 100:1 Range 0,(0.j1% URL+ 0.25% span)

Range : (0.1% URL + 0.15% span)

Model S051T Range 1

+/-(0.025% URL + 0125% span) from 1:1 to 10:1

• (0.05% URL + 0225% span) from 10:1 to 100:1 Static Pressure Effect per 1000 psi (6,9 MPa)

SS1CD Zero Error (can be calibrated out at fine pressure)

+/-0.05% ofURL for line presuras from 0 to 200 psi (O to 1,7 MP Fer static pressures above 2000 pi (13.7 MM, see user manual osemount publication number 00809-0100-4001)

Range 0 *0.125% of spen/100 p (689 kPe)

Range L *0.25% of URL Span Error t0.1% of reading Range 0 *0.125% of pan1100 psi (689 V)

Range 1: *04% of reading 3051P Zero Error (can be calibrated out t ine pressure)

• 0.04% of URL Span Error o.10% of reading

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET - ATTACHMENT B EA-ELECO8-0004 Sheet 29 of 30 Revision I Rosemount Inc.

3051HD Zero Error (can be calibrated out at line pressure) tO.1% f URLforline pressures from 0 to 2000 psi ( to 13,7 M1Pa)

Pbr static pressures above 2000 psi (13,7 NMs) see user manual aeosemount publication number 00809-0100-4001)

Span Error

• 0.2% of reading Dynamic Performance Dead Time and Update Rate applies to all models and ranges, analog output only.

Dead Tine (Te):

45 milliseconds (nominal)

Update Rate:

22 times per econd Total Response Time (Td T):

3051CIP 100 milliseconds for ranges 2-5 255 milliseconds for range 1 700 mIlliseconds for range 0 3051T 100 mIlliseconds for ranges 1-S 3051H/3051L Consult factoy 3051L With liquid level diaphragm in vertical plane, zero shift of up to 1 in~RO (25,4 mmH2O).

Wilth diaphragm in horizontal plane, zero shift of up to 5 inH,0 (127 mmH2O) plus extension length on extended units. All zero shifts can be calibrated out No span effect 3051TICA Zero shifts up to 2.5 nH2O (63,5 mmH2O), which can be calibrated out. No span effect Vibration Effect All Models Measurement effect due to vibrations is negligible except at resonance frequencies. When at resonance frequencies, vibration effect is less than *l% of URL per g when tested between 15 and 2000 Hz in any axis relative to pipe-mounted process conditions.

Power Supply Effect All Models Less han *0.005% of calibrated span per volt.

RFI Effects All Models

• 0.1% of span from 20 to 1000 MHz and for field strenth up to 30 Vhn.

Transient Protection (Option Code TI)

Trsnmkler 4-20 mA Output n.

ims 20m F

g i

Rsponse Th"e

• T T smA 63.2%of TOW FIGURE 3 lpecal Smnart Transmter Response Time Mounting Position Effects 3051C/P Zero shifts up to *1.25 inH20 (0,31 kPa), which can be calibrated out. No span effect 3051H Zero shifts up to t5 inH20 (127 mmH2O), which can be calibrated out. No span effect I

All Models Meets TEE Standard 587. Category B All Models Meets IEE Standard 587, Category B 1 kV crest (lOx 1 000 microseconds) 3 kV crest (8 x 20 microseconds) 6 kV crest (1,2 x 50 microseconds)

Meets IE Standard 472, Surge Withstand Capability SWC 2,5 kV crest, I MHz wave form General Specifications:

Response Ime

- 1 nanosecond Peak Surge Current 5000 amps to housing Peak Transient Voltage 100 Vde Loop Impedance C 25 ohms Applicable Standards IEC 8014, IEC 8014 Note:

Calibrations at 68 *F (20 'C) per ASME Z210.1 (ANSI) t5

PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET - ATTACHMENT B EA-ELEC08-0004 Sheet 30 of 30 Revision I Model 3051 Transmiter for Flow. Level, and Pressure Measurement FUNCTIONAL SPECIFICATIONS Range and Sensor Limits o

M 66120 "W

{_f*UEW NA M

NA MA MA NA asksfjo NA Wo nw A

MA MA KA MA MA i 01 Ws MA~^° s.22^1e2 Ws_

_)

2.5 h4O 25 W2O 250 kH20

-250lO -250 W

0 40

-260 WP

-250 k0H

-260 zo

-250 NW

-40 250 k 062 (0.22 22 s)

(-.

We)

(-42.2 s)

(4-2.2Pa)

(-4.

S)

(-42.2 P*) (-2.2 We)

(-.

W)

I:

10 k*120 100 k6140 1000 lsH3O -I000504n0 O Spula

-10009043

-10005*430.5 oa

-IW05WW3 0.S pea 3 t.4s kft (24.8 kft "2

W) 1-248 0)

(5 WS 9)

(-248 f)

(M W) p(s We ds

{w-s It CUWs SgPl S0pd 300 pl

.eopui 05pui

-300 ud

-300 pal 0.5 -

.3o00ai 0.s gal 420 kt)

(207 Ws) (2 070 m) (-2 070 Ws) (3.5 kpa aba) t-2 70 mfa) (-2 070 W)

(35 Sa ab) (-2 070 kfa) Ps ka go) 2O 20 p200p eOO pl

-2000 pW 0.5 pa

-2000aP Kd K

-2oo0p aS pals

(

(13 bPs) (1 380 bWs) 3SWbks) (-13 oe)

3. kPo *be) (-1t300)

-l3 OM), (35 m al B5.5 innNg)

(260 nintis (O

HP~g) 0.3pd 30 pals Opal 42.07bt)

(20.5bs)

(0 Ws) 12 1.Spl Iflogmi 0pals (IO."____)

(I 034.2bs W4 (O k__

[

Sab BOPpala a

Opa (55.16 UWs) 555 al W

t0 Ws)

L (2758 IPm) 350~)

o0bs TABLE S. Model S051T Range and Sensor Umb (60.3

-a 0

--PO)

-14.0pm) 2 0 1-400 pgs Oal

-14.7 M

_ 06Ps)

(2703 WSP) 407 P) 4-101 Wa) 3 pI 10psi Opa

-14.7 Pt 5 bs)

(5146 iW)

(O W)

(-101 kW) e p eoo si e

-14.7 o 4

tne6 W&)

(27 679 Ws) t

)

1. 101o Ws)

Ioooopwebo vI

° P

-14.7 pi (13 7i kIft)

M kft}

P

)

F101 f)

Zero and Span Adjustment Requirements

• Zero and span values can be set anywhme within the range limits stated in Tables I-&

• Span must be greater than or equal to the minimum span stated in Tables 1-S.

Service Liquid, gas, and vapor applications.

4-20 mA (Output Coda A)

Output Two-wire 4-20 mA, user-selectable for linear or square root output. Digital process variable superimposed on 4-20 mA signal, available to any host that conforms to the HART protocoL Power Supply External power supply required. Standard transmitter (4-20 mA) operates an 10.6 to 56 V dc with no load.

Load Limitations Maximum loop resistance is determined by the voltage level of the external power supply, as described by.

V~~~~~~~~IA Wft.

1:ag gv4Jw cw -

.bm.K.s h. 5.

Q Os 16

ATTACHMENT 4 NUCLEAR MANAGEMENT COMPANY PALISADES NUCLEAR PLANT DOCKET 50-255 October 6, 2003 LICENSE AMENDMENT REQUEST: INCREASE RATED THERMAL POWER -

REFERENCE 9.10: EA-RCH-01-05, Calculation of Chapter 14 Safety Analysis Parameter Changes Due to FC-977 Power Uprate," Revision 1 36 Pages Follow

RierEE1JCE 9./D PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS COVER SHEET EA-RCH-01-05 Total Pages 38 l Tite:CALCULATION OF CHAPTER 14 SAFETY ANALYSIS PARAMETER CHANGES DUE TO FC-977 POWER UPRATE INITTION AND REVIEW Calculation Prelmnary Perdng Final SuPerseded Status Inillated Review Method Revlr*

InlL Detafle Revr.

SR Appd.

Allernate d

Qual AWd.

Appd.

Rev.

DescrIpilon By Date By Calc Review Test By Date By By RGC Harv~ll 91271201 fi:l 1!LA917Q0 a

Original Issue MCnkeHail______

New W

R 7 392002 24 m4 7#o/aa; Terperaure y

PURPOSE:

1)

To identify and quantify all safety analys6 hIputs that are affected by the 1.4% power uprate associated with FC-977 PROCEDURE UTILED:

Admin 9.1

SUMMARY

OF RESULTS:

The proposed power upLrate inpacts several plant parameters that are hIputs into safety analysis. The afigeparameters are listed below with their values at 100% power and at 101.4% power.

I 100%

101.4%

Reactor Power 2530 MW, 2,665.4 MWt Cold Leg Temperature 537.3°F 537.00F Hot Leg Temperature 582.70F 683.0°F Steam Generator Pressure 770 psia 765.8 psla Main Feedwater Temperature 439.5F 440.7 0F Main Steam Flow 11.1 14 Mlbhr 11.297 Mlb^/hr Main Feed Flow 11.174 MlbAir 11.357 Mlb^.hr Steam Generator Liquid Inventory 133,593 lb, 132,531 Ibm Steam Generator Vapor Inventory 8,645 Ibm 8,534 lbm This calculation Is to be considereo Pending until the Dredicted arameters can be validated following imlementation of the oower urate.

I SPECIAL MEDIA ATTACHED (DRAWINGS, MICROFICE, MAGNETIC TAPE, ETC...)

X No _ Yes - List of Attachments Included.

ROCE$ER P

AUG 1 4 2002 ERC-PAL

I -

,,, -

.
..
, I 7,

... - I
I :,.. M-r 7-I

- - 1.

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATON SHEET EA-RCH1-05 Page 2 Rev. I I TABLE OF CONTENTS Section:

Eaae PURPOSE:.......I........,,.

PR O ER UnED...

SUMMARY

OF RESULTS:

I SUM A O F E SULTS:,......

w.......

1 1.0 OBJECTIVE............

3

2.0 REFERENCES

.. S 3.0 ASSUMPTIONS..............................................................................................3......

3 3.1 Mao Assumotion 3

3.2 MinorZZMMo 4

4.0 INPUTSs....tins,...........................................................

4.

5.1 CAl.ation of Reactor.-e r.....................................................

5.2

.Calculationl of PCSemoeratures *-----------s,-,@e---@*------o-ws-@--r--------s 5

5.3 etrnation of Mraximm o e Inlet Temoerature............6................................................................

.5 CaigcuTatnfSTem rat ure 6

5.6 Determination of irain Feedwater Temoatui e

.~.

-- 7

5.

D tinaofSa m

Genetorato.......

-5.9 Disoosltion of Steam Geerator Recirculation Ratio 10 6.0 cONLUSION.............................,.....................................................................................................0 7.0 LIST OF ATTACHMENTS 10

EA-RCH-01.05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Page 3 Rev. I 1 1.0 OBJECTIVE As a result of uncertainty in thermal power measurement the NRC established a 2% margin hi Appendix K. The thermal power measurement equipment currently Installed In nuclear plants Is far more accurate than 2%. The NRC Is permitting plants to execute small power uprates based on the difference between the 2% margin and the justifiable accuracy of the Instrumentation (Reference 1).

is Palisades' ntention to perform a I A% power uprate (FC-977). The objective of this analysis Is to Identify and quantify al safety analysis Inputs that are affected by this modification.

Furthermore. durina the 2001 Refueling Outane, the Palisades hiah oressure turbine was replaced. After start-u.

this resulted In a consistently elevated Main Feedwater temperature In excess of the temperasure predicted for uprate conditions. The pimary puroose of Revision I is to calculate a new Main Feedwater temierature for uorate conditions. A secondary riurose Is to correct an Incorrect assumption. In Revision Oof this analvists.

Assumnion 3.10 stated that `he oressurizer proDortional heaters are assumed to be 60% eneraized.

Discussions with an SRO Indicated that while the proportional heaters are almost lways eneraized. at 2060 osia only 50% of the Droportional heaters are energized." This assumption Is Incorrect In that eV of the heaters are almost always enernized and the Primarv means of ressure control Is Pressurizer spray.

2.O REFERENCES

1.

Small Power Uprates Under Appendix K - Benefits and Considerations. EPRI Technical Report November 2000.

2.

Palisades Updated Final Safety Analysis Report, Revision 22.

3.

Combustion Engineering Analysis 82688-ST-602, Steam Generator Secondary Inventory.

4.

ASME Steam Tables. Fourth Edition, 1979, The American Society of Mechanical Engineers, New York.

5.

Marks' Standard Handbook for Mechanical Engineers. 10 Edition, McGraw Hill, Boston. 1996.

6.

Letter from J.C. Lowry to P.W. Wellhouer, Palisades Repiacement Steam Generator Parameters, ATH-89-238, November 1, 1989.

7.

Letter from G.E. Jarka (Palisades) to R. Wescott (Siemens Power Corporation), New PCS and Core Flow Assumptions, GEJ97*17, October 24, 1997.

8.

EA-PPD-0001, Revision 1, Palisades Cycle 16 Principal Plant Parameters.

9.

Letter from TA Garvin to Burt Stacks, HP Turbine Replacement - Thermal Kt, February 21, 2001.

10.

Letter from TA Garvin to Burt Stacks, HP Turbine Replacement - Correct 100% HB and Correction Curves, May 1,2001.

11.

EA-RCH-02-04. Revision 0. Calculation of Palisades Main Feedwater Temperature and Flowrate and Main Steam Flowrate due to Secondarv Svtem Chances Resultina from High Pressure Turbine Replacement.

3.0 ASSUMPTIONS 3.1 Malor Assumotions 3.1.1 The PCS temperature differential across the core Is assumed to be the difference between hot lg temperature and old leg temperature.

I.......-

EA-RCH-01-05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Page 4 Rev. 1 3.12 Primary coolant leaving the reactor is assumed not to cool down on its way to the steam generator. Hence, the l

PCS temperature entering the steam generator Is the same as hot leg temperature.

3.U PCS mass flow Is assumed to be equally divided among the PCS loops.

I 3.J4 While the overall steam generator u-tube heat transfer coefficient may vary slightly with a change in power, l

Palisades does not have the capability to model the change. Because a 1.4% Increase hI power is sman, the change In heat transfer coefficient Is small. For the purpose of this analysis, the overall heat tnsfer coefficient is assumed to be a constant.

3.j Steam generator pressure at 100% power Is assumed to be 770 psla. It Is risted as 770 psla hI Table 4-4 of l

Reference 2 and in Reference 3. However, a review of plant operating records Indicates that steam generator pressure typically Is between 780 and 790 psla. This Is not considered to be a problem because the current steam aenerator tube oluaaing is between 4% and 5%. Safetvanalvsis credits 15% tube oifric. The saturation temperature associated with 770 psla Is 513.80F (Reference 4).

3.j&

Primaty Coolant Pump power Is assumed to be unchanged by the power uprate.

l 3.j2 Steam Generator Slowdown flow Is assumed to be at is maximum allowed value and at saturated conditions.

l 3.1.8 The pressurizer proportional heaters are assumed to be JDQ% energized. Discussions with the Primary Coolant system englneer Indicated that the proportional heaters are almost always energized.

l 3.J, In the heat balance used to calculate the new Main Steam and Main Feedwater flows, ambient heat osses and l

losses to U ie Non-Regenerative Heat Exchanger In the CVCS system are not modeled because they are not modeled In Reload safety analyses.

3.2 Minor Assumptlons 3.2.1 The incombrg Main Feedwater is assumed to be at Steam Generator pressure.

3.2.2 While the specific heat cavacItv. c. of orimarv coolant is moderately temperature dependent. It Is assumed to be constant for the puroose of this calculation.

4.0 INPUTS 4.1 100% reactor power is 2530 MW, (Reference 2. Table 4-1).

4.2 At 100% power, TAvr, TCw and Tab are 560.00F, 637.3eF and 582.70F. respectively (Reference 2. FIgre 4-9).

4.3 At 100% power, the programmed pressurizer level Is 57% (Reference 2. Figure 4-10).

4.4 The power associated with all four primary coolant pumps Is 15 MW, (Reference 2, Table 4-1).

4.5 The power associated with the pressurizer back-up heaters Is 1,350 kW. The power associated with the pressurizer proportional heaters Is 160 kW (Reference 2, Section 4.3.7).

4.6 Steam Generator maximum blowdown flow at 100% power Is 30.000 IbJhr per steam generator (Reference 2, Section 10.2.1.5).

4.7 The conversion factor from MW, to BTU/hr Is BTUihr = 0.293 W (Reference 5).

EA-RCH-01-05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Page 6 Rev. I 4.8 The enthalpy of Main Steam at the pressure calculated In Section 5A Is 1200.3 BTJIb, (Reference 4).

4.9 The enthalpy of Blowdown at the pressure calculated In Section 5A Is 503.7 BTU/lb, (Reference 4).

4.10 The enthalpy of Main Feedwater at the pressure calculated In Section 5.5 (MinoAssumptlon 3&1) and at the l temperature determined In Section 5.6 Is 420.1 BTUAbm (Reference 4).

4.11 The liquid mass of each steam generator is 203,783 Ib, at 0% power and 133.593 bi, at 100% power. The total mass Inventory of each steam generator Is (Reference 6)

% Power I

Total Mass Pbjt 0

210.759 25 188,925 60 168,583 75 153,V10 100 1

142,138 4.12 The Main Feedwater temerature at 100% power. 2530 MW. Is 439.50F (Reference 12).

4.13 Attachments 1 through 7 show the behavior of Main Feedwater temperature during t1trasonic Flowmeter (UFM) correction factor implementation for the followina dates: Jv 14. 2000: August 10. 2000: September 22. 2000:

November 1. 2000: February 6. 2001: May 25. 2001: and Februarv 20. 2002. These dates reoresent the times within the nest two years In which UFM correction factors were Imnolemented from an uncorrected state.

The basis for the Past two vears is that that Is the available data on the Plant Prooess Comouter.

5.0 ANALYSIS 5.1 Calculation of Reactor Power As discussed in Input 4.1, reactor power is 2530 MW, at 100% power. The power uprate calls for a 1 A% Increase In reactor power. The resulting power Is 2565A MW,.

5.2 Calculation of PCS Temperatures One option to address the Impact of the power uprate on PCS temperature Is to nearly extrapolate the PCS temperature curves of Reference 2, Figure 4-9. from 100% power to 101 A% power. Because this would require changing the plant's PCS temperature program as a function of power and could Impact the risk level of Alloy 600 nozzle cracidng by Increasing hot leg temperature, the decisIon was made to leave the temperature programming as it currently s. However, To* and T, will change as a result of the Increase In core differential temperature associated with an Increase in core power without an Increase In core flowAt 100% power, Tcud and T, are 537.3§F and 582.7F. respectively (Input 42). The core diferential temperature at 101 A% power Is 1=

OA% (TW -Td)roA.

[1 (A~om6.4

=100%

Cd~0 Cold Leg Temperature at 101 A% power Is (ATCdv)101.4% =

ATCoW + TAvE.

121 Hot Leg Temperature at 101.4% power Is

EA-RCH-01.05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Page Rev.

(ATM 6,.4) = TAV 2TC 3

Use of [1), 2] and 31 yields rag and Tft of 537.00F and 583.00F, respectively, at 101.4% power.

5.3 DeterminatIon of Maximum Core Inlet Temperature Per Reference 7. the maximurn core Inlet temperature allowed by the Td iCO equation Is 543.64F. Palisades Safety Analysis assumes a maximum core inlet temperature of 544F (Reference 8). From Section 52, t power uprate decreases Twag from 537.3°F to 537.00F. The maximum inlet temperature assumption remains bounding.

5A Determination of Pressurizer Level Because of the decision not to modify the PCS temperature curves as a result of the power uprate. It is appropriate to maintain Pressurizer level programming as Is. Hence, Pressurizer eel at 101.A% power Is unchanged from the 57% level at the cuenat 100% power (input 4.3).

5.5 Calculation of Steam Generator Pressure and Temperature Heat transfer from the primary coolant to the steam generator Is QSG UA(pc - TsG ).

[4]

where QsG Is the heat transfer rate from the prmary coolant to the steam generator. U is a heat transfer coefficient. A is the heat transfer area, Tpc is average temperature of the primary coolant passing thugh the steam generator and T Is the temperature of the steam generator water.

The average primary coolant temperature used In this calculation, as opposed to the industry standard TAVE is TPC = Tsw. + TSG TM

=

2 where Ts.f Is the temperature of the primary coolant entering the steam generator and T$Gm Is the temperature of the primary coolant leaving the steam generator. As discussed in Malor Assumption 3.iZ, Tsgh Is the same as l THO Ttg, however, is not Identical to Tc because there Is heat addition from the primary coolant pumps. It Is TSGOU - TC1 -ATY, 1 n where ATpcp Is the change In PCS temperature due to heat addition from the primary coolant pumps.

The relationship between reactor power and core differential temperature is OP = hcp(TM - Toad )

7 where OR, is the 100% reactor power of 2530 MW (Input 4.1), oh is the flow rate of PCS water through the reactor and cp is the specific heat capacity of the PCS water (Minor Assumpton 322). Likewise, the relationship l between coolant pump power and pump differential temperature s Qpcp = Mcp P PC)

[8 where Qnp is the primary coolant pump power of 15 MW (Input 4A). m is the flow rate of PCS water through the reactor coolant pumps (Maor Assumption 3.13). TPaOi Identical to Tc, and Tpcph is identical to TxSau,

EA-RCH-0105 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Page Rev. j Because the collective flow rate through the coolant pumps Is Identical to the flow rate through the reactor and because heat capacity Is assumed to be a constant.

(thcp)

=

fi,,

=(m k, P

where k s a constant. [7T and [8] can be ratloed to becorne Qp.

k(TH dd)

QPCP k(Tpmad - TPCF'k }

With substitution and simplification, 110 becomes TSO9J = TCON - QPCP VWc - TCedd)

OR Application of a ratio of 101 A% power and 13% power to (4] yields

[QSG IIO4%

[UA(TpC-TSG)014%

(12]

LQSGJ'OO-A

[UA(T

- TsGc)OO.C A Is a constant because heat transfer area Is not affected. As discussed in Maior Assumption 3.A. U Is assumed to be a constant. 1121 simplifies to

[JSG 6 4%

[Tpc101.4% -1.014 [Tpc -TseGJs%.

113]

Application of Inputs 4.1, 42 and 4A to 111] yields a TGae of 537.0F at 100% power. As discussed In Malor Assumption 3.J.

Tsc Is the same as T,. 582.70F at 100% power. From 5]. Tpc Is 559.90F at 100% power. As discussed in MaLor Assumption 3.jA, Tsr Is 513.80F at 100% power. Application of 1arAssumption 3.16 and the results of Section 5.2 to [11] yields a TGw of 536.70F. From sjsur usm ptlon 3.1j2and the results of Section 5.2, Th Is 583.00F. From [5]. T is 559.90F. Application of 113] yields a T of 513.20F. From Reference 4. the corresponding saturation pressure Is 765.8 psia.

5.6 Determination of Main Feedwater Temperature As discussed In Inout 4.12. the Main Feedwater temperature is 439.5°F at 100% power. 2530 MW. Revision 0 of this analysis had predicted a temperature of 438.5F. which Is an obsolete value. The means of predicting the increase in Main Feedwater temerature as a result of the 1.4% u2rate relies on Main Feedwater temperature behavior when Ultrasonic Flowmeter (UFMI correction factors are Implemented. At plant start-u.

e UFMs are uncorrected such that the correction factor Is 1.00. Application of a correction factor of 0.986 reduces indicated Main Feedwater flow by 1A% and results In calculated calorimetric power being reduced by 1.4%. ermitting a 1 A% (1.00 / 0.986 = 1.014) increase in reactor power. Comoarison of Main Feedwater temoerature before and after implementation of the UFM correction factor allows for prediction of Main Feedwater temperature behavior as a result of a 1.4% ower urate. As discussed In Inout 4.13. data Is available recarding Main Feedwater temperature before and after a UFM correction factor Implementation. The data are shown in the table below.

Each date has two sets of data. The uoner set Is for the AP Steam Generator. and the lower set Is for the Steam Generator. Note that only once In this data set has a UFM been corrected to 0.986.

Data MFW Temperature Before)

MFW emerature After) ifference Correction Factor

.lul 14. 2000 432.3 434.1 1.8

.984 432.4 434.5 2.1 0.981 August 10. 2000 431.8 433.6 1.8 0.984

.1 EA-RCH-01-05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET

_- _ Page Rev. I 431.9 433.6 7

0.981 September 22. 2000 432.3 433.9 1.6 0.985 432.4 434.0 1.6 0.82 November 1. 2000 432.3 432.5 0.2

.985 432.5 432.7 0.2 0.982 February 6.2001 429.2 434.0 4.8 0.984 429.5 434.3 4.8 0.982 May 25,2001 437.5 438.7 12 0Q89 437 9 439.2 1.2083.2 Februarv 20. 2002 438.0 439.2 21 I

1__

438.2 439.4 112 0.983 The data from November 1. 2001. represent a situation in which reactor ower was not Irxeased to the new 100% power followinn implementation of UFM correction factors. The data from February 6. 2001 represent a situation In which power was 6.3%

rior to inDlementation of UFM correction factors nd 99.6% followino Implementation. The rise In power was in excess of 3%. resulting In a slenficant dfference In Main Feedwater temperature before and after Implementation of UFM correction factors. The one time. February 20. 2002. that the correction factor was 0.986. the change In Main Feedwater temoerature was 1.20F. tho same chance seen when a correction factor of 0.989 was implemented on May 25. 2001. While the analyst would exoect the channe In temnerature to be 1.4°F for a correction factor of 0.986 fihe temperature chanqe for a correction factor oF 0.984 was 1.80F. and the chanae for a correction fator of 0.985 was 1.60F..

he only data Polnt available shows a temperature charM of 1.2°F. For tis reason, the predicted increase in Main Feedwater temnerature due to a 1.A% power uorate Is 2 0F. resultino In a Main Feedwater temoerature of 440.70F.

5.7 Caiculation of Main Feedwater and Main Steam Flow Rate To obtain the Main Steam and Main Feedwater flows at 101.4% power, a mass balance and an energy balance must be performed. The fundamental equation for either balance Is Inp - Oup

= Storage.

[14]

For a steady state system, the storage term Is zero. For the mass balance, the Input Is Main Feedwater flow, mh,,. The output terms are Main Steam flow,,,, and Blowdown flow, th faor Assumption 3.1 fl. Hence, the mass balance Is For the energy balance, the Inputs are Reactor power, Pm, the Primary Coolant Pump power, Ppcp, he Pressurizer proportional heaters' power, PR, and the energy associated with the Incoming feedwater. The outputs are the energy associated with the outgoing steam and blowdown flow. The energy balance Is PRv + P

+ PPM + mh,l - tihm

- m hm =0.

(16]

From 15] and 16], the reactor power calculated hi Section 6.1, the pump power of Input 4.4, the pressurizer heater power of Input 4.5 and Maor Assumption 3.j., the Blowdown flow of Input 4.6 and MsLAssumption 3.1.7. and the enthalples of Inputs 4.8, 4.9 and 4.10, the MaIn Steam and Main Feedwater flows are calculatedas follows:

EA-RCH-01-05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Page 0 Rev.1 (60,000 JIbmIhrX503.7 BTUIibm -420.7 BTVllbm.)-

M

= 2530 MW + 15 MW 1.5 MWX1 BTVlbm/0293 WJ106 WIMW) 420.7 B7UI~bm -1200.3 Vibm

= 11,297,000 IbmI hr and mA., = 11297,000 Ibmlhr + 60,000 Ibm/hr = 11,37,000 Ibm/hr, iM 5.8 Determination of Steam Generator Mass Inventory The vapor mass Inventory of each steam generator Is the difference between the total mass hIventory and the liquid mass hventory. From Input 4.11. fte vapor mass Inventory Is 6,976 lb, for 0% power and 4,545 b,, for 100% power, and the liquid mass Inventory Is 210,769 Ibm, for 0% power and 142138 Ibm for 100% power. The steam generator mass Inventory Is 6.01% vapor at J0% power and 3.31% vapor at 0% power, with he vapor percentage Increasing at a rate of 0.027% per percent power. As discussed hI Section 6.6, steam generat pressure decreases from 770 psla to 785.8 psia and temperature decreases from 513.8°F to 3132 0F. Al 770 psa and 513.80F, liquid density is 48.17 lbJft and vapor density is 1.69 Ibft. At 765.8 psa and 5132°F, liquid density Is 4820 b16fts and vapor density Is 1.68 Ib f P. At 100% power, the vapor volume Is 5,0562 fl3, and the liquid volume is 2,773.A ft. The total volume Is 7829.6 ft3. At 101.4% power, the steam generator mass is 6.05%

16.01% + IA

• 0.027%) vapor and 93.95% iquid. The total steam aenerator mass Is mow = mft q

+ mfllq p pqow

• Vfq., + P

• apf Vp,,

L1 where m is mass. D Is density and V is volume. As discussed above.

mftd = 09395 *JmZQ I2 and m,

= 0.0605

• mw It Is also known that VIhW = Vtowd + Vqpu j

=

1191. 1201. 211 and 1221 can be combined into the simultaneous eauations 0.9395

• m P

• V 5

• 0.0605

• ma = Pwp *bW V.,AW)Y Usina liquld density of 4820 Ib,&fP var densitv of 1.68 b,& and a total volume of 7829.6 f. te luid volume is determined to be 2749.6 ft. The vapor volume Is subseauentlv determined to be 5080 nW. With the ebo.ve volumes and densies, the liauid mass Is 132.531 Ibm. nd the vaor mass Is 8634 Ibm.

These steam generator masses are expected to be the correct values at 101 A% power.

I

w I,.-.. -!
z
-,

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET EA-RCH-01.05 Pg2,ORev.j 1

5.9 Disoosition of Steam Generator Recirculation Ratio The steam aenerator recirculation ratios listed In Reference 6 were calculated ushio he CRIBE code. Cumrnt Framatome safety analmsis uses RELAP to model the orlrnarv and secondary systems. The preparer of this calculation has exoerlence In modeling steam enerators in RELAP. While t Is possibie for RELAP to match Uquld Inventory and downconer level wth te CRIBE results. which Is very IkrTpotant for te Lom of Normal Feedwater analysis. It Is ImDossible to match recircuation ratio. In addition, the recirculation rat s a yerv nimn~ftannomMfr n fitn a#u kne inh# bw "A

1. t

^rmnrg h,

0=r AC &Atftm nniAr mrarld n-h 6.0 CRIBE model. For this reason, the recirculation ratio et 101 A% Dower Is not calculated In thIs analysIs.

CONCLUSIONS The proposed power uprate Inpacts several plant parameters that are inputs Into safety analysis.

The parameters are listed below with heir values at 100% power and at 101.4% power.

100%

101A%

Reactor Power 2530 MW 2.664 MW.

Cold Leg Temperature 637.3°F 537.06F Hot Leg Temperature 682 7F 6830°F Steam Generator Pressure 770 psla 765.8 psla Main Feedwater Temperature 439.5F 07rF Main Steam Flow 11.1 14 Mlbhr 11.297 Mlbhr Main Feed Flow 11.14Ml,,hr 1 357MlbJhr Steam Generator Liquid Inventory 133693 Ibm 1

I lbm Steam Generator Vapor Inventory 8.645 Ib 8,634 Ibm 7.0 LIST OF ATTACHMENTS Attachment I - Plant Process Comouter Data for July 14. 2000. UFM Correction Fector Implementation - Plant Process Comouter Data for Auaust 10. 2000. UFM Correction Factor Imolementation - Plant Process Comauter Data for Seotember 22. 2000. UFM Correction Fector Imolementation - Plant Process Comouter Data for November 1. 2000. UFM Cornection Factor Implementation - Plant Process Computer Data for Febrtary 6. 2001. UFM Correction Factor Implementation - Plant Process Computer Data for May 25. 2001. UFM Correction Factor Implementation - Plant Process Computer Data for February 20. 2002. UFM Correction Factor Imotementation - Administrative Reaulred Documents

,

, I -

--
I,,,'

..- -,

.11,

1.
7, 1 1

--
,77,T

• .*-

.

L:~

.2.1I llEA-RCH,.01-.O I,

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Attachment I Plant Process Computer Data for July 14. 2000. UFM Correction Factor Imolementatic Attichmient 1 7 agei Rev.JJ

~~~~~~~~I I 7-~o L Z_

2-

- ^ff

,a.L C/l o U4t-Q -- f r7 lPrJ-e7 I

/A7E DEV I A I UN GRO I

S 1

lUFMCORRSGA 2 UFMCORRSGB 3 HBPWRSTEADY ratio ratio percent 4

07/04/2000 07/04 07/05 07/06 07/07 07/08 07/09 07/10 07/11 07/12 07/13 07/14 07/15 07/16 07/17 07/18 07/19 07/20 07/21 07/22 07/23 07/24 07/ 25 07/26 07/27 07/28 07/29 07/30 07/31 08/01 08/02 08/03 DEV 1

AVE 0.000?

1.000

0. 0

?

1. 0 0 0 0.0 00?

1.0 0 0 C.000?

1.000 0.000?

1.000 0 00?

1.000 i000?

1.000 O O 0?

1. 0 0 0 0

?

1. 0 0 0

0. CO?

1.000 0.08?

0.991 C.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 DEV 2

0.0 0 0 ?

0. 000?

0. 000?

0 0 0 0 ?

0 0 0 0 ?

0.000?

0. 000?

0 0 0 0?

0. 000?

0. 000?

0 0 0 9 ?

0. 000?

0. 000?

0 0 0 0 ?

Q 0 0 0 ?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

AVE 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000

1. 00C 1.000 0.989 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 DEV 3

AVE 1.328 6.180 0.199 3.740 4.078 8.789 0.000 5.482

0. 000*

0.000 18.897 26.712 10.737 89.629 0.100 99.730 0.049 99.830 0.041 99.797 0.500 99.513 0.051 99.778 0.047 99.813 0.039 99.805 0.041 99.805 0.037 99.808 0.040 99.802 0.044 99.800 0.041 99.806 0.041 99.812 0.043 99.805 0.699 99.298 0.260 99.656 0.071 99.839 0.040 99.904 0.044 99.891 0.048 99.904 0.049 99.894 0.042 99.916 0.065 99.875 0.047 99.887 DEV 4

AVE

,.~~~~~~

~~~~

I.,

It...

I OK a,.

U..

-M-9,9-02--0f

/

A P UVVI - 8 i M - 5 1TT_0708A 2TT_0706A 3 FEEDWTR-FLOWSGAAVG 4 FEEDWTR-FLOWSGBAVG deg F deg F lbm/hr lbm/hr 07/04/2000 07/04 07/05 07/06 07/07 07/08 07/09 07i10 07/11 07/12 07/13 07/14 07/15 07/16 07/17 07/18 07/19 07/20 07/21 07/22 07/23 07/24 07/25 07/26 07/ 27 07/28 07/29 07/3 0 07/31 08/01 08/02 08/03 DEV 0.7 4

1.2 4 2 1.180 19.183

.33 8

2.749

.191

0. 223

.149 0.131 0.747 0.099 0.101

. 092 0.091 0.107 0.092 0.109 0.131 0.118

0.

14

0. 324 0.277 0.122 0.103 0.102 0.101 0.101 0.104 0.126 0.110 AVE 70.865 70.425 69.450 89.958 129.839 243.619 422.173 432.219 432.357 432.346 433.083 434.058 434.081 434.090 434.048 433.979 433.990 434.054 434.022 434.028 434.071 433.747 433.966 434.195 434.237 434.223 434.186 434.164 434.248 434.239 434.173 DEV 0.784 1.223 1.184 22.668 1.467 109.077 11.148 0.219 0.139 0.116 0. 84 0.102 0.121 0.117 0.096

0. n 96 0.125 0.112 0.123 0.124 0.114 0.331 0.222 0.197 0.123 0.092 0.095 0.084 0.104 0.096 0.096 2

AVE 70.849 70.399 69.414 93.899 123.382 247.874 422.226 432.265 432.41 432.389 433.244 434.461 434.490 434.479 434.431 434.389 434.405 434.461 434.425 434.449 434.467 434.129 434.232 434.413 434.594 434.585 434.543 434.544 434.592 434.597 434.556 DEV 34192.0 26959.1 2988 7 6 0.000 0 000A 10021 23 6 355 65 7199.12 4156.11 4212 93 47791.0 39 42.28 3851.27 3 503. 73 4315.96 3412.23 3588.35 3699.04 3549.75 3682.94 3651.09 39900.7 16273.2 4941.08 3564.75 3507.93 3909. 72 3829.30 3624.36 4729.41 4213.12 3

AVE 118852 67746.7 395807 138297 0.000 1209583 4866886 5466386 5469356 5463045 5507500 5571645 5573120 5573129 5569615 5568568 5566505 5566124 5566032 55656 53 5565292 5535786 5557231 5568436 5571180 5570861 5570595 5570102 5571771 5569020 5569528 DEV 106604 30936.3 90345.7 0.000 i.

0' 0

• 1013088 651571 7763.25 4226.60 4076.88 50523.2 4172.98 3788.66 3632.56 4203.96 3478.01 3807.93 3685.65 3602.75 3871.81 3617.74 41520.7 16123.4 4940.71 3462.56 3797.94 4156.38 4000.90 3844.12 4795.81 3613.98 4

AVE 320689 156116 181381 185245 0.000 1287959 4930974 5552585 5557325 5550988 5597758 5665268 5668021 5667111 5664117 5661896 5660027 5659270 5659158 5660299 5660180 5628698 5650100 5660489 5664402 5663132 5664568 5663848 5665571 5663382 5663618 I

lug OK mn.

MEN.

OEM

EA-RCH-01-05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET IPage I Rev.

1 Plant Process Computer Data for Aucust 10. 2000. UFM Correction Factor ImplementationI

-- m EAd-Pc.

-Cpt A#

f 2.

LA-V I~~

A TTNSGRUP-2

__~~~~~~~~~~~~~~~~~~~~

S0 lUFM-CORRSGA 2 UFM-CORR-SGB 3 HB-PWR -TEADY 4

ratio ratio percent 08/04/2000 08/04 08/05 08/06 08/07 08/08 08/09 08/10 08/11 08/12 08/13 08/14 08/15 08/16 08/17 08/18 08/19 08/20 08i21 08/22 08/23 08/24 08/25 08 / 26 08/27 08/28 08/29 08/30 08/31 09/01 09/02 09/03 DEV 1

AVE 0.984

.u04?

0.985 0.000?

1.000 0.00?

1.000 0.0

?

1.000 A0

' ?

1.000 0.038?

0.991 C.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0,000?

0.984 0.000?

0.984 000 ?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 DEV 2

AVE 0.000?

0.981 0.004?

0.982 0.000?

1.000 0.000?

1.000

. 0 00?

1. 0 0 0 0.000?

1.000 0.009?

0.989 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0,000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.001?

0.981 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 DEV 0.039 2.962 0.08 0.053 1.066 1.843

0. 524 0.051 0.045

0. 041 0.041 0.092 0.047 0.040 0.042 0.042 0.043 0.048 0.042 0.100 0.212 0.255 0.041 0.0 5 5 0.041 0.045 0.041 0.044 0 0 3 7 0.041 0.049 3

AVE 9 9.8 9 6 98.666

92. 660

92. 6 40 92.197 99.043 99.375 99.213 99.252 99.237 99.237 99.288 99.416 99.444 99.415 99.41 6 99.410 99.400 99.397 99.396 99.078 99.2 6 5 99.383 99.410 99.449 99.398 99.440 99.431 99.417 99.399 99.444 DEV 4

AVE I

Nu tL OK N,

&FA-Pf-tJ -0C)L4 AoCAcA--

Z uwI 8 N I -I 1TT_0708A 2 TT_0706A 3 FEEDWTRFLOW_SGAAVG 4 FEEDWTR_FLOWSGBAVG deg F

deg F lbm/hr lbm/hr 08/04/2000 DEV 1

AVE 08/04 08/05 08/06 08/07 08/08 08/09 08/10 08/11 08/12 08/13 08/14 a 8/15 08/16 08/17 08/18 08/19 08/20 08/21 08/22 08/23 08/24 08/25 08/26 08/27 08/28 08/29 08/30 08/3 1 09/01 09/02 09/03 3.6 4i 0.14.

C.14 0.9 6 3 1.4 9 9 0.569

• i 6

0.116

'.115 0.100 0.107 0.397 0.120 0.132 0.129 C.15 2 0.135 Q 1 1 5 0.12 0.116 0.117 0.107 0.108 0.

1 6 0

1 1 0 0 10212 0.110 434.162 432.675 424.403 424.474 424.380 431.838 432.982 433.581 433.542 433.583 433.633 433.721 433.831 433.735 433.766 433.704 433.674 433.678 433.763 433.790 433.527 433.722 433.848 433.776 433.695 433.719 433.698 433.716 433.720 433.689 433.718 DEV 0.130 3.8 70 0.185

0. 109 0.977 1.487 0.540 0.128 0.129 0.117 0.121 0.163 0.121 0.076 0.112

0. 099 0.114 0.104 0.130 0.139 0.131 0.182 0.123 0.115 0.103 0.102 0. 121 0.125 0.188

0. 0 9 1 0.095 2

AVE 434.540 432.974 424.284 424.373 424.292 431.905 433.048 433.619 433.612 433.644 433.669 433.751 433.667 433.589 433.633 433.583 433.581 433.536 433.646 433.657 433.412 433.633 433.709 433.634 433.585 433.615 433.591 433.617 433.864 433.925 433.924 DEV 3500. 74 198932 6 386.25 4761. 49 62781.0 1097 86 32883.8 3922.08 3807.18 3213.07 3455.44 6498.68 3827.73 3386.76 3816.32 3491.39 3609.56 4047.38 3556.57 6572.70 12328.4 14852.6 3595.99 3959.23 3679.44 6115.48 4982.33 3822.53 3607.91 3550.85 3673.15 3

AVE 5569526 5486884 5024175 5023624 4995757 5415943 5496849 5533840 5536113 5534996 5532491 5536465 5544050 5545097 5542373 5541602 5541131 5540998 5541933 5542317 5523477 5535295 5542668 5543740 5545643 5538900 5545221 5542120 5541358 5540189 5543634 DEV 3634.94 207254 6616.60 5383. 74 62704.6 1125 32 34112.2 4 262.38 3791.34 3641.86 3691.63 6519.01 4042.28 3625.69 3869.50 3580. 94 3610.43 3644.49 3636.61 7022.11 12704.0 15297.8 3613.93 4111.90 3 621.08 5525.71 4889.74 3912.95 3522.27 3737. 01 4371.54 4

AVE 5664293 5578098 5092945 5090383 5064109 5499418 5582828 5621500 5623343 5623093 5621227 5623954 5630866 5631696 5629717 5628297 5628253 5626733 5627033 5626678 5605929 5618469 5625776 5626452 5628208 5623109 5629373 5624674 5625258 5624497 5626744 I

OK liEU,,

-U-

-- -7

. I

.
-_ 7 1,

EARCH01.O5 I PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Page I Rev.

i Plant Process Comauter Data for September 22. 2000. UFM Correction Factor Implementation I

Z A

it

-4..

_^%

9 G &-S l

S.

SH

-/

-h J

P

__--VIAIIUN (jHUUP 21 lUFM-CORR-SGA 2 UFM_COF.RSGB 3 HBPWRSTEADY 4

ratio ratio percent 09/04/2000 09/04 09/05 09/06 09/07 09/08 09/09 09/10 0 9/ 1 1 09/12 09/13 09/14 0 9/ 1 5 09/16 09/17 09/18 09/19 09/20 09/21 09/22 09/23 09/24 09/25 09/26 09/27 09/28 09/29 09/30 10/01 10/02 10/03 10/04 DEV

.000?

0?

20 O0?

0 0?

00 0?

00 ?

0.00 0?

. 00

?

0.00 0?

0.00 0?

0.0080?

0.00 0?

0.00 0?

0.00 0?

0.00 0?

0.00 0?

0.00 0?

0.00 0?

0.00 0?

0.00 0?

0.000O?

0.000O?

0.000O?

AVE 0.984 0.984 0.999 1.000 1.000 1.000 1.000 1.000 1.000

1. 000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 0.992 0.985 0.985

. 985 0. 985 0. 985 0. 985 0. 985 0. 985 0. 985 0. 985 0. 985

? O. 985 DEV 0.00 0.00 0. 00 0.00 0.00

0. 00 0.00 0.00

0. 00 0.00 0.00 0.00 0 00 0. 00 0 00 0. 00 0.00 0.00 0.00 0.00 0.00 0. 00 0.00 0. 00 0.0 0 0. 00 0

00

0. 00 0. 00 0.00 o.

0 2

0?

0?

3?

0?

OC?

0?

0?

0?

0?

0?

0?

0?

0?

0?

0?

0?

0?

9?

9?

0?

0 ?

0?

0?

0 ?

0?

0?

0 ?

0 ?

0 ?

0 ?

?

AVE 0.982 0.982 0.999 1.000 1.000 1.000 1.000 1.000 1.000

1. 00C 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 0.991 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 DEV 3

AVE 0.050 99.447 20.151 91.375 0.0 0 0 0.0 0 0.000 2.689 0.000#

0.000 0.0 0 0 0.0 0 0.000#

0.000 0.000#

0.000 0.000*

0.000 0.000 4.562 0.0 0 0 0.0 0 0.554 4.656 0.380 3.143 15.886 32.609 9.901 90.917 0.071 99.873 0.042 99.911 0.041 99.907 0.504 99.663 0.045 99.897 0.047 99.911 0.042 99.899 0.043 99.903 0.043 99.910 0.414 99.591 0.068 99.871 0.042 99.899 0.047 99.918 0.045 99.899 0.045 99.917 0.042 99.903 DEV 4

AVE 11 OK U,,

ENO EN, IN I........

...I I; r : i i :Z'ia;.:

v-t..._............... '..IA i: i..........,..

-:;i...

I I,....i-....-

k r-; >it I........ L.

r r

1 2

3 4

V I -

I vi I -

I TT_0708A TT_070bA FEEDWTR-FLOW-SGA-AVG FEEDWTR-FLOW-SGB-AVG deg F deg F ibm/hr ibm/hr 09/04/2000 09/04 0 9/ 0 5 09/06 09/07 09/08 09/09 0 9/ 1 0 0 9/ 1 1 09/12 09/13 09/14 0 9/ 1 5 09/16 09/17 09/18 09/19 09/20 09/21 09/22 09/23 09/24 09/25 09/26 09/27 09/28 09/29 09/3 0 10/01 10/02 10/03 10/04 DEV 0.120 34.202 28.6'3 9.884 3.074 i.953 1.627 l G.030 3.463 6.355 4.515 3.584 10.590 78.221 0.489 0.148 0.118 0.115 0.749 0.124 0.099 0.114 0.113 0.117 0.321 0.162 0.128 0.129 0.116

0. 1 1 5 0.123 AVE 433.531 420.650 216.355 142.966 126.403 118.351 112.145 110.183 194.532 176.561 158.014 144.118 137.787 308.090 423.416 432.442 432.413 432.334 432.762 433.905 433.843 433.719 433.783 433.851 433.456 433.852 433.954 434.065 434.024 434.047 433.907 DEV 0.126 32.614 98.287 10.791 2.839 2.283 1.950 11.174 4.438 5.848 4.231 3.033 8.917 66.255 10.604 0.147 0.093 0.121 3.743 0.096 0.119 0.087 0.112 0.110 0.311 0.147 0.098 0.117 0.119 0.116 0.103 2

AVE A 33.765 421.120 338.930 152.776 137.490 128.830 121.448 115.772 188.789 171. 15 153.937 141.553 138.749 313.246 423.719 432.820 432.529 432.443 432.911 434.040 433.975 433.851 433.911 433.982 433.601 434.015 434.100 434.167 434.094 434.125 434.034 DEV 4033.90 1276003 0.000 24221.6 0. 000 0.000*

117458 0.000*

0.000*

23169.8 0 000*

0.000*

10137.7 878588 591630 5055.71 3399.46 3638.61 48125.6 3416.23 3923.78 3621.41 3875.31 3769.20 24740.8 4762.81 3598.84 3926.39 4387.32 3642.06 3470.29 3

AVE 5542592 5008151 1 0 1 1 1 102803 0.000 0.000 249474 0.000 0.000 69334.7 0.000

0. 000 141344 1571488 4940044 5473847 5474970 5476758 5516197 5582068 5582174 5580226 5580809 5581972 5561209 5577364 5578300 5579526 5575721 5574667 5573588 DEV 4417.03 1301719 61648.4 O.0 0 0 9 0.000*

0. 000 0.000*

142869 0.000 C. 00 0 75002.4 18489.9 900539 604667 5553.12 3766.49 3849.89 49840.2 3968.99 3766.34 3800.48 3373.10 3742.42 25573.0 4681.58 3776.15 3820.32 4169.21 3563.78 3787.85 4

AVE 5625678 5080301 173336 0.0 0 0 0.000 0.000 0.000 0.000 291481 229197 0

O.000 199823 60379.0 1566621 5001578 5555702 5555989 5558427 5599322 5668520 5668754 5667712 5668503 5669223 5648473 5664794 5666037 5668469 5663730 5663656 5661483 a

9 OK OEM MEN MEN

.. -... ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~,.,,~~~~-

-7 7 -

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Aftachment 4 Plant Process Computer Data for November 1. 2000. UFM Coleton Factor Implementation o,,.

,,.,, r.

' I -' I' ' '.. T I

, I I I I I.

.E -RC oq h dm4 -4 Ui--VA_-FUN G-RUUP 21 1

2 3

4 UFM_COn.R_SGA UFMCORRSGB HBPWRSTEADY rat io ratio percent 10/ 05 /2000 10/05 10/06 10 07 10/08 1 0/ 0 9 1 0/ 1 0 1 0/ 1 1 10/ 12 10/ 13 10/14 10/ 15 10/ 16 10/ 17 10/18 1 0/ 1 9 10/20 10/21 10/22 10/ 23 10/24 10/25 10/26 10/27 10/28 10/29 10/30 10/31 11/ 0 1 11/ 02 11/03 11/ 04 DEV

-i r,

^. 0 0?

O

.00?

0 00?

0.000?

0.

0 0?

C.

0 0 ?

0.

0 0 0 ?

0.0 00?

0.0 00?

0.0 00?

00?

0 000?

0. 000?

0.006?

0.0 00?

0.0 00?

0.0 08?

0.000?

O.0 00?

0.000?

0.000?

AVE 0.985 0.985 0.985 0.985 0.985 0.985 0.984 0.984

0. 984 0.984

0. 984 0.984 0. 984 0.984

0. 984

0. 984

0. 984 0.984 0.984 0.984 0.984 0.984 0.987 1.000 1.000 1.000 1.000

0. 993 0.985 0.985 0.985 DEV

0. 0 00

0. 0 00

0. 0 00?

0. 000#

0 000?

0 000?

0. 001

0. 000?

Q. 0C0?

0. 000

0. 000

0. 000

0. 000

0. 000

0. 000

0. 000

0. 000

0. 000

0. 000

0. 000

0. 000

0. 000

0. 007?

0. 000

0. 0 0

0..000?

0. 000?

0. 009?

0. 000

0. 000

0. 000 2

AVE 0.982 0.982 0.982 0.982 0.982 0.982

?

0.982

?

0.981

?

0.981 0.981

?

0.981

?

0.981

?

0.981 0.981

?

0.981 0.981

?

0.981 0.981 0.981 0.981 0.981

?

0.981

?

0.984 1.000 1.000

?

1.000

?

1.000

?

0.992 0.982 0.982 0.982 DEV 0.048 0.046 0.043 0.043 0.043 0.043 0.053 0. 041 0.047 0.046 0.042 0.042 0.040 0.040 0.045 0.044 0.043 0.039 0.046 0. 041 0.719 0.070 20.246 0.922 13.814 3.371 0.067 0.841 0.046 0.047 0.052 3

AVE 99.911 99.904 99.916 99.918 99.914 99.923 99.913 99.916 99.914 99.912 99.913 99.900 99.899 99.906 99.903

99. 919 99.913 99.914 99.911 99.910 99.273 99.877 87.376 50.631 61.685 97.308 99.900 99.131 98.332 98.308 98.260 DEV 4

AVE OK so,i' on MEi UUt

_I Dw..

I 0 -0 1TT_0708A 2 TT_0706A 3 FEEDWTRFLOWSGA_AVG 4 FEEDWTR-FLOW-SGB-AVG deg F deg F lbm/hr lbm/hr 10/05/2000 DEV 1

AVE 10/05 10/06 10/07 10/08 1 0/ 0 9 1 0/1 0 1 0/ 1 1 10/12 10/13 10/14 1 0/ 1 5 10/16 10/17 10/18 1 0/ 1 9 10/20 10/21 10/22 10/23 10/24 0.126 0.123 0.116

.117 0.137 0.'16 0.'23 0.119 0.135 0.132 0.132 0.131 0.141 0.135 0.142 0.135 0.146 0.186 0.152 0.127 0.390 0.154 26.260 1.572 19.611 3.010 0.148 0.141 0.117 0.121 0.118 433.

433.

433.

433.

433.

433.

433.

433.

434.

434.

434.

433.

433.

433.

433.

433.

433.

433.

433.

434.

871 848 868 744 890 986 999 984 039 075 045 942 874 871 931 973 949 895 980 001 DEV 0.107 0.098 0.092 0.088 0.135 0.112 0.116 0.113 0.131 0.119 0.126 0.104 0.120 0.105 0.116 0.120 0.110 0.164 0.130 0.096 0.381 0.132 26.116 1.564 19.576 2.920 0.134 0.137 0.111 0.077 0.120 2

AVE 434.028 434.028 434.050 433.823 433.972 434.129 434.156 434.131 434.184 434.230 434.195 434.085 434.038 434.050 434.084 434.119 434.095 434.040 434.121 434.152 433.622 434.087 418.399 370.880 387.157 430.083 432.480 432.539 432.684 432.599 432.486 DEV 47 3 0.1 8 3810.86 3940.24 3722.16 4021.79 3464.67 5666.04 3663.84 3936.42 3790.40 3838.59 3339.91 3555.49 3960.83 3978.95 3939. 79 3578 66 3597.55 4013.53 3952.29 41466.6 5306.16 12281 7 4 51414.6 806698 201216 5265.93 5465.63 3706.15 3868.42 4280. 71 3

AVE 5571250 5568920 5569937 5568421 5569165 5571181 5578347 5583958 5585976 5586535 5587103 5587753 5587665 5589253 5591202 5593867 5593423 5592205 5593512 5593234 5554704 5590714 4829497 2587786 3227488 5324818 5474429 5470418 5474726 5472494 5469069 DEV 4480.95 4031.21 3689.68 3722.18 3824.53 3705.34 5488.20 3521.47 3982.99 3869.38 4016.38 3283.68 3415.09 4253.83 4392.93 3389 61 3920.80 3827.55 3718.17 3503.69 43285.2 5053.83 1253356 51435.3 818164 204722 5090.86 5148.51 3982.28 4009.40 3925.84 4

AVE 5658965 5657298 5657843 5656696 5658016 5658830 5666160 5671717 5673471 5673365 5674348 5675628 5674684 5676647 5679205 5681485 5680741 5681094 5681006 5681768 5641224 5679413 4900936 2614416 3267680 5397359 5553933 5550087 5554857 5552550 5549136 10/25 10/26 10/27 10/28 10/29 10/30 10/31 11/01 11/ 02 11/03 11/04 433.465 433.951 418.166 370.389 386.690 429.834 432. 300 432.354 432.496 432.408 432.292 11 a

a OK U,,,

Z Z

P~~~~~~~~.

-~....

• c0-oz-014 A

1. 4 B4 i

4 ULVIATIC)N Ci 21 I UFMCOhR-SGA 2 UFMCORRSGB 3 HB-PWRSTEADY ratio ratio percent 4

11/05 / 2000 11/05 1/06 11/07 11/08 1 /

5 11/10 1 1/ 11 11/12 11/13 11/14 11/15 11/16 11/17 11/18 1 1/ 1 9 11/20 11/21 11/22 11/23 11/24 11/25 11/26 11/27 11/28 1/29 11/30 12/01 12/02 12/03 12/04 12/05 DEV 1

AVE 3.OO?

0.985 00?

0.985 3.OCO?

0.985 200?

0.985 00 0 ?

0.984 J 00?

0.984

?.3 00?

0.984 0 ?

0.984 OD0?

0.984 00?

0.984 0.0?

0.984 S3?

0.984

000?

0.984

>000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 0.000?

0.984 DEV 2

AVE 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.001?

0.982 0.000?

0.981 0.00C?

0.981 0.000?

0.981 0.000?

0.98_

0.000?

0.981 0 000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 00 00?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 0.000?

0.981 DEV 0.054 0.051 0.066 0.4 76 0.050 0.047

0. 046 0.043 0.047 0.045 0 0 49 0.044 0.050 0.048 0.051 0.044 0.043 0.048 0.052 0.044 0.050 0.043 0.046 0.055 0.049 0.4 1 3 0. 043 0.049 0.049 0.049 0.050 3

AVE 98.273 98.294 98.293 99.313 99.568 99.605 99.611 99.595 99.609 99.598 99.592 99.593 99.593 99.590 99.604 99.601 99.593 99.610 99.604 99.622 99.640 99.627 99.632 99.626

99. 615 99.347 99.605 99.610 99.627 99.607

99. 615 DEV 4

AVE

'I IOU OK OE.

R on.

Il I JcL,+/- 4 Uw I

8 1

UT 1-5--

~

~

~

~

~

~

~

~

~

~

~

S 0

Z 1 TT_0708A 2 TT-0706A 3 FEEDWTR-FLOW-SGA-AVG 4 FEEDWTR-FLOW-.SGB-AVG deg F deg F lbm/hr lbm/hr 11/05/2000 1 1/ 0 11/06 11/07 11/08 1 1/ 0 9 11/10 1 1/ 1 1 11/12 11/13 11/14 11/15 11/16 11/17 11/18 11/19 11/20 11/21 11/22 11/23 11/24 11/25 11/26 11/27 11/28 11/29 11/30 12/01 12/02 12/03 12/04 12/05 DEV 1

AVE 0.132 432.291 0.123 432.336 0.128 432.377 0.470 433.284 0.163 433.549 0.144 433.649 0.143 433.632 0.152 433.576 0.157 433.525 0.178 433.618 0.154 433.739 0.156 433.759 0.158 433.764 0.156 433.744 0.174 433.790 0.160 433.771 0.165 433.772 0.149 433.760 0.168 433.769 0.166 433.815 0.165 433.861 0.166 433.902 0.185 433.935 0.180 433.867 0.181 433.831 0.326 433.605 0.176 433.775 0.181 433.712 0.178 433.748 0.181 433.754 0.190 433.656 DEV 0.117 0.116 0.102 0.462 0.143 0.115 0.112 0.118 0.127 0.153 0.120 0.123 0.124 0.125 0.127 0.124 f.112 0.105 0.117 0.127 0.125 0.122 0.120 0.111 0.112 0.302 0.120 0.127 0.123 0.118 0.137 2

AVE 432.497 432.553 432.588 433.495 433.766 433.863 433.851 433.792 433.775 433.855 433.961 433.966 433.967 433.952 433.978 433.955 433.971 433.961 433.959 434.004 434.069 434.107 434.151 434.067 434.047 433.833 434.006 433.953 433.995 433.986 433.897 DEV 4327.07 3951.29 4740.56 29666.4 5456.89 3684.57 3687.96 3792.72 3794.92 3470.90 3452.34 2711.50 2996.39 2978.75 3249.62 2495.09 6002.52 2852.91 3613.59 2551.92 3022.03 2597.49 2725.56 3161.87 2867.12 23086.5 2587.75 3239.75 3130.08 2966.85 3037.76 3

AVE 5469759 5469684 5468721 5531587 5549860 5556202 5556091 5554853 5555995 5555737 5555289 5555416 5555858 5555543 5556297 5556642 5555756 5557675 5556394 5558606 5559718 5559525 5559798 5558782 5558109 5543111 5557339 5556873 5558606 5556702 5556588 DEV 4520.13 4248.10 4601.47 31045.0 5736.30 3592.40 3682.40 3293.27 3748.26 3752.46 3474.65 2412.19 2990.26 2976.37 2999.98 2845.28 7566.30 2658.47 3056.38 2694.18 2530.95 2724.32 2664.43 3174.27 3076.03 24740.6 2634.85 2582.70 2595.79 2917.75 2852.74 4

AVE 5550120 5550120 5549957 5615295 5634466 5640351 5641262 5639613 5639618 5640111 5641689 5641660 5641608 5641231 5642379 5641821 5642121 5641840 5642499 5643198 5645173 5644248 5645172 5644479 5643542 5625933 5642723 5642851 5643869 5643353 5643096 I.-

.u OK EN Laon

'E

I I

a, i I.

I I

I PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET FAtACH01-"

l rI

.ZMI Rev-l APachment 6 Plant Process Computer Data for February 6. 2001. UFM Correction Factor Imloementation I

-,4 7..."-.:

I

.-"" ~

-~,

I

=

I

~~~

a 7

f

.EA-RC#-oz-o h5 7

MM IPA I~~ IO UH A

P 21 S

lUFMCCeF.R-SGA 2 UFM.4CORRSGB 3 HBPWRSTEADY 4

ratio ratio percent 01/ 06/2001 01/ 06 01/ 07 01/08 0 1/ 0 9 0 1/ 1 0 0 1/ 1 1 01/ 12 01/ 13 0 1/ 1 4 0 1/1 5 01/ 16 01/17 01/ 18 0 1/ 1 9 01/20 01/21 01/22 01/23 01/24 01/25 01/26 01/27 01/28 01/29 01/30 01/31 02/01 02/02 02/03 02/04 02/05 DEV 0.00 0?

0.000?

C 0C?

0.000?

5.000?

0.

00?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.009?

0.000?

0.007?

0.000?

0.000?

0.000?

0.000?

0.000?

0.006?

0.000?

0.000?

0.000?

AVE 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.983 0.991 1.000 0.996 0.983

0. 983 0.983 0.983 0.983 0.986 1.000 1.000 1.000 DEV 2

AVE 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0. 982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0. 982 0.000?

0.982 0.000?

0. 982 0.000 ?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.009?

0.991 0.000?

1.000 0.008?

0.995 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.000?

0.982 0.006?

0.984 0.000?

1.000 0.000?

1.000 0.000?

1.000 DEV 0.048 0.050 0.049 0.052 0.051 0.480 0.047 0.051

0. 0 5 1 0.050 0.050 0.052 0.047 0.046 0.047 0.047 0.512 0.064 0.050 4.789 3.967 0.484

0. 117 0.041 0.051 0.050 0.047 21.735 2.158 8.482 5.078 3

AVE 99.906 99.913 99.907 99.900 99.907 99.511 99.904 99.912 99.888 99.910 99.901 99.923 99.896 99.911 99.916 99.912 99.579 99.887 99.904 94.678 96.219 99.620 99.840 99.903

99. ' )6 99.912 99.913 86.030 53.083 58.146 96.381 DEV 4

AVE

~~~OK Eu

A of t

A.

AL f-r l

. 0i -

J-" Wt-L~cJf Ift1?4 J^s4J $

r4 le.1 L)WvI -8

/ M-lb 1TT_0708A 2 TT-0706A 3 FEEDWTR-FLOW-SGA-AVG 4 FEEDWTR-_FLOW_SGBAVG deg F

deg F lbm/hr Ilbm/hr 01/06/2001 01/ 06 0 1/

7 01/ 08 0 1/ 0 9 01/10 0 1/ 1 1 01/12 01 /13 01/ 14 01/ 15 01/ 16 01/ 17 01 8

01/19 01/20 01/ 21 01l/ 22 01/23 01/ 24 01/25 01/26 01/27 01/28 01/29 01/30 01/31 02/ 01 02/02 02/03 02/ 04 02/05 DEV

0. 2 5 5 70 0.260 3.263

.266 0.404 0.262 0.263 0.263 0.265 0.268 0.264 0.265 0.272 0.270 0.267 0.391 0.274 0.268 5.467 3.841 0.592 0.304 0.283 0.281 0.281 0.282 28.228 3.393 12.362 4. 600 AVE 434.011 434.035 433.950 433.875 433.991 433.724 434.084 434.089 434.069 434.124 434.097 434.105 434.039 434.069 433.984 433.995 433.771 434.055 434.031 427.688 428.836 432.286 433.826 433.953 434.021 433.930 433.903 416. 208 374.724 382.553 429.221 DEV 0.148 0.150 0.146 0

. 140 0.143 0.341 0.144 0.149 0.147 0.142 0.137 0.134 0.136 0.134 0.1 46 0.142 0.320

0. 154 0.138 5.480 3.834 0.543 0.193 0.144 0.157 0.140 0.145 28.086 3.377 12.385 4. 545 2

AVE 434.290 434.303 434.224 434.152 434.227 433.960 434.331 434.322 434.298 434.350 434. 349 434.356 434.283 434.316 434.241 434.239 433.995 434.288 434.264 427.882 429.043 432.514 434.050 434.162 434.228 434.146 434.124 416.508 375.152 382.938 429.487 DEV 2966.36 3050.75 3118.18 3067.43 2970.30 27338.4 2940.27 2929.61 2968.45 3209.40 3037.60 3088.11 2826.60 3455.93 2941.19 3476.65 29119.1 3696.45 4575.61 343884 242283 32813.0 8543.20 4076.51 4469.37 4184.45 4071.77 1310674 117262 493575 303061 3

AVE 5575392 5576257 5575338 5573942 5575160 5551264 5576261 5575904 5575328 5577066 5576571 5577663 5575589 5578038 5579522 5580547 5563830 5581678 5584771 5217579 5258914 5490811 5588690 5593989 5594430 5592478 5593176 4751256 2727272 3016281 5266002 DEV 4

AVE 2639.04 5662913 2871.82 5663102 2344.13 5662087 3108.29 5661048 2783.34 5662371 29142.2 5638179 2660.42 5662864 2909.94 5663888 2836.50 5661394 2775.89 5663059 2460.89 5662230 2931.59 5663943 2533.66 5661627 2511.32 5664498 2620.65 5664624 3177.57 5665917 29979.2 5648261 4770.50 5668847 4511.90 5671197 351550 5295463 245746 5334371 33448.4 5574729 8195.95 5676606 3301.15 5681883 3651.10 5682665 4119.07 5684081 3778.84 5683411 1338477 4822503 122272 2758782 501418 3054789 310617 5344857 OK

_E__

men9 11

m m

I Ir IL V -

0,1

.O Ifv

.vf !(Y -L -t f/ffoA4.Ap'.%&

b 9

A N2 W_

7

=

z

_~~~~~~~~~~~~~~~~~~~~~B S

i I

lUFMCORRSGA 2 UFMCfRRSGB 3 HBPWRSTEADY 4

r a t i o r a t i o percent 02/ 06 / 2001 02/ 06 02/ 07 02/08 02/09 02/10 02/ 11 02/ 12 02/ 13 02/14 02/ 15 02/ 16 02/ 17 02/18 02/ 19 0 /20 02/ 21 02/22 02/23 02 /24 02/2 5 02/26 02/27 02/28 03/01 03 i 2

03/03 03/04 03/05 03/06 03/07 03/08 DEV 1

AVE 0.C8 ?

0.991 0.3O00?

0.984 O0.G00?

0.984

.0C?

0.984 O0.

?

0.984

0.

0 ?

0.984 C0C0?

0.984 Q0.0

?

0.984

.OO?

0.984 o.0nOG?

0.984 Q nOO?

0.984

0. 00 ?

0.984

0.

0 ?

0.984 0.000G ?

0.984 0.000 ?

0.984 0.00 0 ?

0.984 0.000 ?

0.984 0.

0

?

0.984 0.000 ?

0.984 0.000 ?

0.984 0.000 ?

0.984 0.000 ?

0.984 0.000?

0.984 0.000 ?

0.985 0.000 ?

0.985 0.000 ?

0.985 0.000 ?

0.985 0.000 ?

0.985 0.000 ?

0.985 0.000 ?

0.985 0.000 ?

0.985 DEV 2

AVE 0.009?

0.000?

0.000?

0.000?

0.003?

0.000?

0.000?

3.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0.000?

0 0 0 0?

0.000?

0.000?

0.000?

0.000?

0.000?

0.990 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982

0. 9 d2 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.982 0.981 0.981 0.981 0.981 0.981 0.981 0.981 0.981 DEV 0.503 0.049 0.046 0.051 0.049 0.043 0.044 0.044 0.043 0.045 0.045 0.044 0.047 0.043 0.045 0.046 0.042 0.051 0.043 0.183 0.392 0.044 0.044 0.046 0.047 0.044 0.050 0.045 0.041 0.046 0.045 3

AVE 99.673 99.897 99.917 99.916 99.907 99.907 99.908 99.913 99.902 99.891 99.910 99.904 99.903 99.894 99.903 99.893 99.899 99.904 99.912 99.868 99.701

99. 893 99.912 99.889 99.910 99.907 99.913 99.900 99.902 99.914 99.899 DEV 4

AVE 1-lug l OK Nis

~~~~M IN I

0t I

A1

.t I r-1D

-rt

=f--

at Uz.

.tT th J

rec

)

__-8iMtl 1 TT-07n8A 2 TT-0706A 3 FEEDWTRFLOWSGAAVG 4 FEEDWTRFLOWSGBAVG deg F

deg F

ibm/hr lbm/hr 02/

02/

02/

02/

02/

02/

02/

02/

02/

02/

06/2001 06 07 08 09 10 1 1 12 13 14 02/15 02/16 02/17 02/18 02/19 02/20 02/21 02/22 02/23 02/24 02/25 02/26 02/27 02/28 03/01 03/02 DEV 0.838 0.268 0.267 0.280 0.265 0.169 0.118

0. 120 0.106 0.112 0.117 0.108 0.118 0.123 0.114 0.11 O.1lil 0.113 0.112 0.242 0.394 0.101 0.104

0. 114 0.116 0.111 0.119 0.127 0.124 0.113 0.114 AVE 433.034 434.016 434.133 434.086 433.867 433.949 433.988 434.096 434.189 434.211 434.248 434.134 434.135 434.223 434.244 434.089 434.090 434.138 434.225 434.171 434.054 434.259 434.238 434.272 434.312 434.418 434.405 434.260 434.286 434.381 4-3 4.3 6 4 DEV 0.8 1 5 0.129 0.141

0. 155

0. 127

0. 109 0.093 0.123 0.099 0.099

0. 096 0.098

0. 104

0. 090

0. 085

0. 100 0.122 0.117

0. 100 0.235 0.410

0. 118 0.099 0.098

0. 097 0.098

0. 110 0.116 0.112

0. 077 0.089 2

AVE 433.300 434.286 434,396 434.361 434.143 434.096 434.087 434.192 434.259 434.2S5 434.289 434.185 434.208 434.289 434.300 434.161 434.155 434.213 434.297 434,215 434.124 434.326 434.289 434.339 434.366 434.469 434.451 434.326 434.397 434.455 434.415 DEV 47742.3 4245.91 4134.75 4333.60 4246.15 3551.56 3855.22 4252.55 3682.17 3860.95 3761.04 3880.68 4160.43 3775.94 3942.01 3857.12 3918.57 3989.21 3404.44 11916.1 23915.2 4037.03 4006.54 3998.57 3609.58 3948.71 3970.27 3833.88 3709.58 3684.53 3886.91 3

AVE 5515309 5573616 5575506 5575117 5572379 5573830 5574183 5574404 5572186 5568174 5570111 5568835 5568777 5568419 5569999 5567983 5567659 5568714 5569666 5567559 5557474 5569825 5572231 5570728 5571076 5571909 5572032 5570539 5570521 5572079 5 5 71238 DEV 49492.3 3844.22 3734.16 3844.63 3751.61 3714.37 3836.62 3898.08 3908.54 3630.27 3775.59 3625.79 3364.95 3589.68 3570.99 3807.50 3436.23 4155.57 3582.07 11952.8 25401.2 3611.82 3682.11 4234.24 3905.78 3574.32 3988.84 3455.69 3461.62 3764.22 3795.81 4

AVE 5602548 5663244 5665346 5664976 5662860 5661560 5661460 5662190 5660435 5663765 5664684 5663200 5663425 5664203 5663931 5662090 5663117 5663832 5665109 5661391 5651223 5663233 5667383 5664152 5664776 5665202 5665481 5663475 5664249 5665246 5664113 03103 03/04 03105 03/06 03/ 0 7 03/08 H_

OK Iu.alu.

. 1.

I EA-RCH01- 05 I

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINUATION SHEET Pale Rev.

Attacnent 6 Plant Process Computer Data for May 25. 2001. UFM Correction Factor Imotementation l7

. EA-R-C,#4-oz-oqt A4dt &&

6/

RP4e~, 2 S 3 ~~~~~~~~~~~~~~~~

3gm U,

a,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

S S

65~~11k r~ilom 1IUFM-.CORR-_SGA 2 UFM_.CORP-_

GB 3 HB-_PWR-_STEADY 4

r a tio r a tio percent 0 5/15 2 200 1 0 5/15 0 5/16 0 5/17 05/1 8 0 5/19 05/2 0 0 5/21 0 5/22 0 5/23 0 524 0 525 0 526 0 527 0 528 05/2 9 05/ 3 0 0 531 0 601 0 602 0 603 0 604 0 605 0 606 0 607 0 608 06/0 9 0 610 0 611 0 612 0 613 0 614 DEV C.

00?

00?

C0300?

0.0 00?

000?

0.0 00 ?

0.0 00?

• 0 0 0 0.0 00?

0.0 00?

0.0 00?

0.0 00?

0.0 00?

0.0 00?

0.0 00?

0.0 00?

0.0 00?

0.0 00?

0.0 01?

0.0 00?

0.0 00?

AVE 1.0 00 1.00 0 1.00 0 1.00 0 1.00 0 1.00 0 1.0 00 1.0 00 1.0 00

1. 00 0 0.99 4 0.9 89 0.9 89 0.9 89 0.9 89 0.9 89 0.98a9 0.9 89 0.9 89 0.9 89 0.9 89 0.9 89 0.9 89 0.9 89 0.9 89 0.98a9 0.9 89 0.9 89 0.98 8 0.98 8 0.98 8 DEV 0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 08 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

0.0 00 ?

2 AVE 1.00 0 1.00 0 1.00 0 1.00 0 1.0 00 1.0 00 1.00 0 1.00 0 1.00 0 1.00 0 0.9 91 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 83 0.9 82 0.9 82 DEV 1 0.59 5 0.1 21 0.0 57 1 1.64 8 2.2 32 2.3 23 0.0 49 0.0 70 0.0 57 0.0 47 0.4 16 0.0 56 0.0 48 0.0 46 0.0 44 0.0 44 0.0 52 0.0 44 0.0 48 0.05 0 0.0 43 0.0 44 0.0 43 0.0 47 0.0 46 0.0 52 0.0 48 0.0 49 0.0 48 0.0 43 0.0 50 3

AVE 5 3.46 2 4 9.7 09 4 9.68 5 5 9.1 21 8 8.34 5 9 8.7 17 9 9.91 1 9 9.9 04 9 9.90 1 9 9.9 02 9 9.7 28 9 9.8 96 9 9.92 4 9 9.9 16 9 9.9 05 9 9.90 1 9 9.9 02 9 9.90 5 9 9.9 09 9 9.9 14 9 9.91 0 9 9.9 17

99. 9 19 9 9.93 5 9 9.9 18 9 9.91 4 9 9.91 1 9 9.91 1 9 9.91 0 9 9.9 06 9 9.9 16 DEV 4

AVE Ng.

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1 TT_0708P 2 TT_0706A 3 FEEDWTRFLOW_SGAAVG 4 FEEDWTRFLOWSGBAVG deg F deg F lbm/hr lbm/hr 05/ 1 5 / 2001 0 5 / 15 0 5 / 16 05/ 17 05/18 05/ 19 05/20 05/ 21 05/22 05/23 0 5 / 24 0 5 / 25 05/26 05/27 05/ 28 05/29 0 5 / 30 05/ 31 06/01 06/ 02 06/ 03 06/ 04 06/05 06/ 06 06/ 0 7 06/ 08 06/09 06/10 06/11 06/ 12 06/13 06/ 14 DEV I

AVE 16.

0.

0.

17.

0.

0.

0.

G.0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

O.

O.

567 226 114 804 536 1l9 131 118 106 0 99 585

. 1 9 098 112 106 113 125 1 10 136 150 127 114 114 1 05 113 120 1 11 121 112 132 1 19 376.631 370.973 370.879 386.700 425.879 436.649 437.716 437.531 437.560 437.540 438.022 438.694 438.692 438.693 438.705 438.660 438.721 438.680 438.737 438.961 439.144 439.225 439.253 439.252 439.232 439.168 439.155 439.158 439.218 439.356 439.421 DEV 16.093 0.226 0.080 17.482 2.588 2.168 0.104 0.115 0.097 0.092 0.607 0.099 0.123 0.086 0.088 0.096 0.118 0.082 0.121 0.130 0.106 0.075 0.081 0.112 0.111 0.095 0.091 0.104 0.117 0.126 0.110 2

AVE 3 7.685 372.258 372.178 387.761 425.861 436.809 437.972 437.901 437.944 437.929 438.441 439.176 439.193 439.196 439.189 439.161 439.211 439.170 439.227 439.328 439.401 439.466 439.487 439.505 439.483 439.427 439.410 439.421 439.488 439.616 439.667 DEV 611604 6967.77 3885.38 674780 135984 140730 3859.64 5271.88 3969.26 3635.98 41171.9 4425.75 3694.75 3776.80 3548.74 3413.63 4206.44 3780.46 3733.96 4191.13 3906.05 3475.62 3719.08 4134.96 3966.50 3851.54 4016.83 3911.33 4904.96 3882.52 3923.99 3

AVE 2747531 2529039 2527085 3074591 4783668 5415581 5484358 5482136 5482569 5482737 5518706 5569724 5571587 5571573 5570515 5569995 5570771 5570593 5571682 5572662 5570258 5569772 5569656 5568606 5565721 5564865 5564906 5564657 5567773 5570307 5570354 DEV 628849 7570.76 3349.70 693443 140326 146333 3975.86 5168.18 4350.25 3691.99 42056.0 4300.14 3904.12 3330.16 3547.87 3809.68 3845.82 3338. 81 4027.08 3749.69 4440.79 3703.08 3542.81 4654.88 3804.90 4098.98 3586.15 3509.90 5186.09 3770.10 3926.69 4

AVE 2807498 2582090 2580920 3144220 4904157 5562258 5634200 5633267 5633471 5633676 5670749 5723162 5724985 5723986 5723543 5723215 5723718 5723619 5723959 5726135 5724828 5723877 5724502 5722305 5718842 5718536 5717738 5717903 5720920 5723590 5723122 I

OK

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PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CONTINuATION SHEET Plant Process Computer Data for February 20. 2002. 11FM Correction Factor Ir I..

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U WIHNGUP2 1 UFMCORRSGA 2 UFMCORP-SGB 3 HB _ PWR._ STEADY ratio r a t i o percent 4

02/ 18 / 2002 02/ 18 02/ 19 02/20 02/21 02/22 02/ 23 02/24 02/ 25 02/26 02/ 27 02/28 03/ 01 03/ 02 03/ 03 03/ 04 03/05 03/ 06 03/ 07 03/ 08 03/09 03/10 03/ 11 03/12 03/ 13 03/14 03/ 1 5 03/16 03/17 03/ 18 03/ 19 03/20 DEV 1

AVE 0.00 0 ?

1.000

. Q0'J?

1.000 0.007 ?

0.994 0.000 ?

0.986 0.000 ?

0.986 0 500 ?

0.986 0.000 ?

0. 9 86 0.000 ?

0.986 0.000 ?

0.986 C.000 ?

0.986 0.000 ?

0.986 0.000?

0.986 0.000 ?

0.986 0.0 00?

0.986 0.000 ?

0.986 0.000?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000 ?

0.986 0.000?

0.986 0.000?

0.986 0.000?

0.986 0.000?

0.986 0.000?

0.986 DEV 2

AVE 0.000?

1.000 0.0 0?

1.000 0.008?

0.993 0.000?

0.983 0.000 ?

0.983

0. 000?

0.983 0.000?

0.983

0. 000?

0.983

0. 000?

0.983 0.000?

0.983

0. 000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000 ?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000 ?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 0.000?

0.983 DEV

0. 041 0.051 0.561 0.053

0. 042 0.049 0.044 0.043 0.04 5 0.049 0.043 0. 045 0.047 0.046 0.050 0.046 0.044 0.042 0.046 0.041 0.044 0.045 0.047 0.042 0.182 0.045 0.049 0.040 0.045 0.0 46 0.043 3

AVE 99.993 99.989 99.658 99.957 99.980 99.995 99.993 100.006 100.005 99.998 99.994 99.986 100.015 99.984 100.007 100.004 99.985 99.995 99.990 100.004 99.999 99.989 99.998 99.995 99.937 99.467 99.435 99.481 99,464 99.486 99.489 DEV 4

AVE OK mo i

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1TT_0708A 2 TT_0706A 3 FEEDWTRFLOW-SGA-AVG 4 FEEDWTR-FLOW-SGB-AVG deg F deg F ibm/hr Ibm/hr 02/ 1 8/ 2002 02/ 18 02/ 19 02/20 02/21 02/22 02/23 02/24 02/25 02/26 02/27 02/28 03/ 01 03/ 02 03/03 03/04 03/ 05 03/06 03/ 0 7 03/ 08 03/ 09 03/ 10 03/ 11 03/ 12 03/ 13 03/ 14 03/15 03/16 03/17 03/ 18 03/ 19 03/20 DEV

.1 4 39

0. 1 00 0.039

'. 113 I

?.

'.127 0.393 0.145 0.109 0.125 0.102 0.107 0.127 0.100 0.107 0.113 0.136 0.116 0.116 0.107 0.229 0.114 0.116 0.125 0.107 0.121 0.113 AVE 437.966 438.031 438.339 439.232 439.285 439.356 439.357 439.306 439.198 439.098 439.135 439.084 439.054 439.077 439.140 439.141 439.229 439.292 439.300 439.237 439.007 439.215 439.326 439.337 439.161 438.689 438.685 438.755 438.872 438.886 438.892 DEV 0.111 0.105 0.482 0.106 0.077 0.096 0.125 0.126 0.090 0.129 0.103 0.128 0.101 0.110 0.067 0.078 0.128 0.109 0.089 0.152 0.092 0.109 0.098 0.104 0.215 0.094 0.101 0.085 0.107 0.114 0.108 2

AVE 438.095 438.182 438.488 439.420 439.471 439.502 439.509 439.497 439.405 439.343 439.423 439.351 439.307 439.298 439.367 439.371 439.480 439.504 439.499 439.379 439.232 439.447 439.501 439.545 439.404 438.939 438.950 438.998 439.059 439.055 439.040 DEV 3801.10 4032.86 35312.2 4130.16 3856.73 3915.02 3769.17 3659.01 3829.36 3705.79 3717.99 3927. 24 4356.90 3602.94 3821.54 3769.32 3708.33 3614.47 4624.93 3744.71 3674.95 3767.35 4244.09 3836.18 11755.7 3698.44 3766.39 3564.43 3545.09 3724.15 3833.44 3

AVE 5471266 5469986 5489532 5561701

'5562908 5563930 5564560 5564996 5563877 5562949 5563568 5562096 5563529 5560937 5563296 5564749 5566682 5566510 5569937 5573080 5570957 5571901 5571496 5571463 5567278 5537345 5535485 5538647 5538336 5539492 5540998 DEV 3903.42 4010.88 35733.7 4289.54 3803.16 3614.93 3733.30 4123.79 3410.26 4157.35 3488.62 3748.07 3419.18 4130.77 3741.41 3508.71 3615.57 3886.36 4521.01 3751.22 3514.37 3683.31 4031.46 3599.55 12084.8 3625.93 3909.24 3321.00 3531.13 3752.61 3548.33 4

AVE 5643776 5642763 5663453 5736705 5739009 5740251 5739639 5740036 5739570 5738311 5738108 5737539 5739281 5738376 5740944 5742396 5742752 5744562 5746800 5748342 5747153 5749033 5749650 5748456 5743289 5713021 5710795 5714236 5713835 5715648 5715110 I

.,on OK ME, JOE

' E

W_

EACH0145 l PAISADES NUCLEAR PLANT

,NMIEERING ANALYSIS CONTINUATION SHEET I_

_&a1 1eD fl