ML11124A126
| ML11124A126 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/28/2011 |
| From: | Gillespie T Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2010-001, Supplement 2 | |
| Download: ML11124A126 (120) | |
Text
{{#Wiki_filter:T. PRESTON GILLESPIE, JR. Eniker Vice President nrgy, Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Hwy. Seneca, SC 29672 864-873-4478 864-873-4208 fax T.Gillespie@duke-energy.com April 28, 2011 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1, 2 and 3 Renewed Facility Operating Licenses Numbers DPR-38, -47, -55; Docket Number 50-269, 50-270 and 50-287; Response to Request for Additional Information Regarding License Amendment Request to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles License Amendment Request (LAR) No. 2010-001, Supplement 2 On May 6, 2010, Duke Energy Carolinas, LLC (Duke Energy) submitted a LAR requesting Nuclear Regulatory Commission (NRC) approval to extend Oconee Nuclear Station (ONS) Technical Specification 18-month Surveillance Requirement frequencies to 24 months in accordance with the guidance of Generic Letter 91-04, "Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle." Duke Energy provided a response to a November 26, 2010, NRC Request for Additional Information (RAI) by letter dated February 11, 2011. The NRC electronically transmitted another RAI on April 5, 2011. The enclosures to this letter provide the requested information. If there are any questions regarding this submittal, please contact Boyd Shingleton of the Oconee Regulatory Compliance Group at (864) 887-4716. I declare under penalty of perjury that the foregoing is true and correct. Executed on April 28, 2011. Sincerely, T. Preston Gillespie, Jr., Vice President Oconee Nuclear Station
Enclosures:
- 1. Duke Energy Response to NRC Request for Additional Information
- 2. Duke Energy Documents Acky www. duke-energy.corn
U. S. Nuclear Regulatory Commission April 28, 2011 Page 2 cc w/
Enclosure:
Mr. Victor McCree, Regional Administrator U. S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. John Stang, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8 G9A Washington, D. C. 20555 Mr. Andy Sabisch Senior Resident Inspector Oconee Nuclear Site Ms. Susan E. Jenkins, Manager Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St. Columbia, SC 29201
ENCLOSURE 1 Duke Energy Response to NRC Request for Additional Information
April 28, 2011 Page 1 Enclosure I Duke Energy Response to NRC Request for Additional Information (RAI) RAI I In Attachment 2 to the letter dated February 11, 2011, the licensee listed Calculation OSC-9852 in the AFAL (As-Found and As-Left) Analysis column for SR 3.3.1.7 in Table 3.3.1-1, Reactor Protective System Instrumentation. In Section 3.3 of this calculation OSC-9852 the licensee stated:
"The Digital RPS and ESFAS modifications provide certification for all new instrumentation for calibration intervals up to a maximum of 30 months. From Section 9.3 of Reference 4.E (Reference 4.E is the Oconee Nuclear Station Digital RPS/ESPS License Amendment Request (LAR) 2007-09 (ADAMS Accession No. ML080730340),
dated January 31, 2008):
"Specific TXS module operating history in terms of total module years and number of faults or failures were evaluated. All the TXS modules mean time between failure (MTBF) observed data support a CHANNEL FUNCTIONAL TEST at an 18 month plus 25% interval by about two orders of magnitude.
In addition, in Section 3.3.15 of Reference 4.E:
"The results of the hardwarereliabilityanalysis also support extending the surveillance testing interval for channel functional tests to once per 18 months, since the hardware availabilityanalysis was based on assuming a 24 month surveillance testing interval."
Therefore, an AFAL Drift Analysis is NOT required for those portions of an RPS and ESFAS System that have been replaced." The staff finds that the above statements do not demonstrate conclusively that the RPS/ESFS (sic) Digital System is adequate for 24 month fuel cycles. Provide justification to demonstrate why the new RPS/ESFS (sic) Digital System is suitable for calibration intervals of 24 month, extrapolated to a maximum 30 months to permit for a grace period of 25%. Duke Energy Response to RAI I AREVA Document No. 51-9044432-004 (Oconee Nuclear Station Surveillance Changes Justification) provides the basis for extending the 92-day Channel Functional Test frequency to 18 months. This document was docketed earlier in support of the License Amendment Request (LAR) for the digital Reactor Protective System (RPS)/Engineered Safeguards Protective System (ESPS) upgrade by letter dated September 30, 2008. Duke Energy provided a copy of this document to the NRC electronically on March 30, 2011. From Section 4.2.1, Channel Functional Test and Drift, of this document; "This low failure rate, combined with the continuous comparison of redundant analog signals for deviations, reasonably supports a surveillance test interval for calibration of 18 months plus 25% and also an interval of 24 months plus 25%." Although the document supports a nominal calibration interval of 24 months, Duke Energy did not request an extension of the surveillance at that time. Also, AREVA Document No. 51-9004194-001 (Clarification of Accuracy Specifications for TELEPERM XS Modules SAAI, SNVI, and S466) provides additional details on the specifications for the TXS modules. Based on this
- Duke Energy Response to NRC Request for Additional Information April 28, 2011 Page 2 vendor documentation, all the instrument uncertainty calculations for the replacement RPS/ESPS digital system support a maximum 30-month calibration interval.
Also, as documented in Section 5.11 of OSC-9719 "Instrument Drift Analysis Methodology in Support of 24-Month Surveillance Interval," Oconee has in place a continuing calibration surveillance procedure review program. This program verifies that loop/component as-found calibration values do not exceed acceptable limits as defined in applicable instrument uncertainty calculations, except on rare occasions (entered in corrective action program for evaluation). Once the 24-month Technical Specification Surveillance Requirement intervals have been approved and implemented, this calibration surveillance procedure review program will continue to verify that future loop/component as-found calibration values do not exceed the acceptable limits determined in the associated instrument uncertainty calculations as revised to reflect a 30-month calibration frequency, except on rare occasions. The cited AREVA documents and the uncertainty calculations, coupled with the calibration surveillance monitoring program, provide adequate justification for a 24-month calibration interval for the replacement RPS/ESPS digital system.
RAI 2
Section 6.1.3 in Calculation OSC 9852 states, "Per Section 6.1.2.C, the drift allowance for replacement digital RPS/ES bounds a 30 month calibration." Section 6.1.2.C of OSC-9852 refers to OSC-8856, Revision 1, "Digital RPS Neutron Overpower (Neutron Flux) and Pump Power/Flux Trip Function Uncertainty Analysis." Both OSC-9852 and OSC-8856 refer to a number of other documents. The staff could not access several of these documents from the licensee's website: Extranet.haifire.com/sites/duke_rps/default.aspx. As an example for completing review of OSC-9852 the staff would need to review the following documents: A. EDM 102, Rev. 3, Instrument Setpoint/Uncertainty Calculations, dated February 15, 2005 B. OSC-9904, Revision 0, Technical Specification Surveillance Procedure Historical Study in Support of 24 Month Fuel Cycles. C. OSC-7237, Revision 1, RPS High Flux and Power/Pump Monitor Trip Function Uncertainty Analysis Calculation. D. OSC-8828, Revision 2, Digital RPS RCS Pressure & Temperature Trip Function Uncertainties and Variable Low RCS Pressure Safety Limit Calculation. E. OSC-6733, Revision 4, Wide Range Nuclear Instrumentation Loop Uncertainty Calculation. F. OSC-2820, Revision 32, Emergency Procedure Guideline Setpoints. G. OSC-4310, Revision 0, RVLIS Uncertainty Analysis for Oconee Units 1, 2, and 3.
- Duke Energy Response to NRC Request for Additional Information April 28, 2011 Page 3 H. OSC-2578, Revision 9, Wide Range Reactor Building Water Level Instrument Loop Accuracy Calculation.
- 1. OSC-3315, Revision 3, FDW Pump Turbine Hydraulic Oil Pressure Loop Instrument Accuracy Calculation.
J. Power Range Calibration Procedures IP/1/AI0301/003 E, Revisions 49, 61, 93, 85, and 84. As an alternative, the licensee may be able to provide the necessary information to justify that the tolerance parameters used in the uncertainty analysis are valid for a maximum of 30 month calibration interval and will ensure a 95/95 confidence level in a suitable way without providing all the documents listed above. This is applicable for several other documents the licensee listed in the letter dated February 11, 2011. Duke Energy Response to RAI 2 The calibration tolerance values used in the uncertainty analyses are based on vendor specifications for the instrument components that comprise the loop function. The calibration tolerance values specified in the uncertainty analyses are appropriately reflected in the associated instrument calibration procedure. For as-left and as-found calibration setting tolerances, they are set equal to each other in the instrument calibration procedures. For most instrument loops (excluding the replacement RPS/ESPS digital system), direct addition of the reference accuracies is used to establish the as-left/as-found calibration tolerances. No allowances for drift, Measurement and Test Equipment (M&TE) errors or resolution are included in the establishment of the calibration setting tolerances. The reference accuracies used are based on manufacturer specifications for reference accuracy which are taken at a 95/95 confidence level unless otherwise noted by the manufacturer. The treatment of reference accuracy specifications as 95/95 unless otherwise noted by the manufacturer is typical industry practice. Setting the as-found tolerance equal to the as-left tolerance is conservative. For the replacement RPS/ESPS digital system, a similar approach is taken with the exception that the as-left/as-found tolerances are established based on the square root sum of the squares (SRSS) combination of the reference accuracies and M&TE uncertainties for the applicable loop function. The uncertainty calculations for the replacement RPS/ESPS digital system calculate an "as-found" tolerance which includes drift. This "as-found" tolerance is used as the engineering out of tolerance notification limit in the associated instrument calibration procedure. This approach ensures any as-found readings that exceed the limits documented in the uncertainty calculations are reviewed by engineering for evaluation and appropriate corrective action while maintaining the site standard of setting the as-left and as-found calibration tolerances to the same value. The above methodology can be verified by reviewing the as-left/as-found setting tolerances within the calibration procedures and manufacturer specifications for a given instrument loop. For the instrument applications within the scope of the 24-month cycle LAR, a check was performed in each drift calculation to ensure the 30-month analyzed drift exceeded the. applicable as-found/as-left setting tolerance for each function. The intent of the review was to ensure current procedure tolerances are acceptable both from an as-left and as-found standpoint.
- Duke Energy Response to NRC Request for Additional Information April 28, 2011 Page 4 Generic Letter 91-04, Changes In Technical Specification Surveillance Intervals To Accommodate A 24-Month Fuel Cycle, only refers to calibration setting tolerances in the following sense. From Enclosure 2 Item 6: "6. Confirm that all conditions and assumptions of the setpoint and safety analyses have been checked and are appropriatelyreflected in the acceptance criteria of plant surveillance procedures for channel checks, channel functional tests, and channel calibrations.
Licensees should take care to avoid errors or oversights when establishing acceptance criteria for plant surveillance procedures that are derived from the assumptions of the safety analysis and the results of the methodology for determining setpoints. The NRC staff experience is that licensees have encounteredproblems when asked to confirm that instrument drift and other errors and assumptions of the safety and setpoint analyses are consistent with the acceptance criteriaincluded in plant surveillance procedures. This review should include channel checks, channel functional tests, and the calibrationof channels for which surveillance intervals are being increased." The focus of item 6 is to ensure acceptance criteria in plant procedures, including calibration tolerances, are in alignment with assumptions or values used in the safety analysis and not on the specific methodology used to establish calibration setting tolerances. The instrument drift calculations and associated uncertainty calculation reviews conducted for the 24-month fuel cycle project ensured the values used in Duke Energy safety analysis calculations and procedures are in alignment.
RAI 3
In the letter dated February 11, 2011, the licensee stated, "At ONS, as-found calibration tolerances are conservatively set equal to as-left calibration tolerance." The staff notes that in Section 7.4 of the calculation OSC-8856, and in several other calculations, the licensee has used reference accuracy, drift, setting tolerance, measurement and test equipment, and resolution uncertainty parameters in calculating as-found tolerance. Please provide justifications for why all these parameters can be used in calculating as-left tolerance, especially the drift parameters. Duke Energy Response to RAI 3 Calculation OSC-8856 documents the uncertainty of the RPS Neutron Overpower (Neutron Flux) and Pump Power/Flux Trip Function for the replacement RPS/ESPS digital system. As stated in the response to RAI 2 above, the "as-found" calibration tolerances, calculated in uncertainty calculations for the replacement RPS/ESPS digital system, are used as the engineering out of tolerance notification limit in the associated instrument calibration procedure. As-found calibration tolerances specified in the instrument calibration procedures are conservatively set equal to as-left tolerances. As-left calibration tolerances are determined as described in the response to RAI 2. Drift effects are not included in the determination of as-left/as-found calibration tolerances specified in the calibration procedures.
- Duke Energy Response to NRC Request for Additional Information April 28, 2011 Page 5 For the balance of the uncertainty calculations, an as-found or acceptable limit value is determined in a similar manner as the "as-found" tolerance noted from OSC-8856. The engineering out-of-tolerance notification limits specified in the applicable instrument calibration procedure are established to be equal to or conservative with the acceptable limit.
RAI 4
In the Attachment 6 to the letter dated May 6, 2010, and in several other calculations, it is stated that for Unit 2, the 24-month fuel cycle will precede the digital RPS/ESFS (sic) upgrade. For several instrument channels in Unit 2 credit is being taken for the CHANNEL FUNCTIONAL tests to substitute the CHANNEL Calibration. Section 2, TS 3.3.1, Reactor Protective System (RPS) Instrumentation, in Enclosure 2 of LAR 2007-09, states that the CHANNEL FUNCTIONAL TEST is a subset of the CHANNEL CALIBRATION. Provide justifications why, for Unit 2, the CHANNEL FUNCTIONAL TEST can substitute for the CHANNEL CALIBRATION, especially for the existing instruments (prior to the operation of the digital RPS/ESFAS system) where the entire instrument channel is calibrated during the refueling outages. Duke Energy Response to RAI 4 This response is only applicable to Unit 2 due to implementation of 24-month cycles prior to the installation of the RPS/ESPS digital system. The Channel Functional Tests are only being credited for the Channel Calibration with regard to drift of the analog Bailey RPS and ESPS cabinet electronics. The channel calibration surveillance requirements will continue to be met. The same calibration steps, relative to the original Bailey RPS and ESPS cabinet electronics, are performed during a Channel Functional Test as are performed during a Channel Calibration. The Channel Functional Test is performed on a more frequent basis than the Channel Calibration. Therefore, for that part of the loop, the Channel Functional Test fulfills the requirement of the Channel Calibration. In other words, the Channel Functional Test effectively addresses the drift of the cabinet electronics and will continue to do so with implementation of 24-month cycles. The drift of the instrument loop sensors that are calibrated on an 18-month outage frequency was addressed in the applicable instrument drift calculations and the results were evaluated for impacts to the associated uncertainty calculation.
RAI 5
In several calculations AFAL data has been provided for Multi-Cycle and Single Cycle data collection format, e.g. OSC-9819. Explain the significance of the Multi-Cycle data. Duke Energy Response to RAI 5 The overall significance of the multi-cycle data is that it is used in the primary technique to validate the instrument drift methodology standard assumption of moderate time dependency relative to drift in the AFAL data which ultimately affects how the 18-month data is extrapolated
- Duke Energy Response to NRC Request for Additional Information April 28, 2011 Page 6 to determine the Analyzed Drift for 30 months. The discussion below provides an overview of why the multi-cycle data is collected, how it is obtained and how it is used in the instrument drift calculations to better illustrate the significance of the data.
For instrument drift, the drift methodology document assumes moderate time dependency in the AFAL data as a standard approach (Reference Section 4.9.3 of OSC-9719 "Instrument Drift Analysis Methodology in Support of 24 Month Surveillance Interval"). This assumption is based on the content of Sections 4.9.1 and 4.9.2 of OSC-9719 and the associated references. Various techniques, as described in the remainder of Section 4.9, are then used to support or refute this assumption. The primary technique used is the review of multi-cycle data. The loop and/or component AFAL data from (typically) two 18-month calibration intervals is combined to obtain the multi-cycle data. Using multiple interval raw data eliminates the potential for data grooming by only selecting intervals where the instrumentation was NOT reset, and increases the number of data sets which enhances the statistical results. This method is similar to that described in section 4.3 of the NRC Status Report (Reference 8.1.3 of OSC-9719): "acceptable ways to obtain this longer-interval data include.., combining intervals between which the instrument was not reset or adjusted". The average and standard deviation of the multi-cycle data is calculated and is compared to the average and standard deviation of the single-cycle data. If there is a significant time dependency in the bias portion of the analyzed drift, then this time dependency would cause the average of the multi-cycle data to drift uniformly in one direction relative to the average of the single-cycle data. Likewise, if there was a significant time dependency in the random portion of the analyzed drift, then this time dependency would cause the standard deviation of the multi-cycle data to expand relative to the standard deviation of the single-cycle data. The time dependency would be manifested in the ratio of the multi-cycle standard deviations to the single-cycle standard deviations. If the ratio of the standard deviations indicates a significant increase, then the associated Analyzed Drift is judged to be strongly time dependent. Otherwise, the single-cycle data will always be considered to be moderately time dependent per the assumption identified in Section 4.9.3 of OSC-9719 above. For the Analyzed Drift random term, a "significant increase" in the value of the ratio of the standard deviations of the multi-cycle data and the single-cycle data is considered to be equal to or greater than the value of the square root of the ratio of the average multi-cycle data calibration interval and the average single-cycle data calibration interval (i.e., the square root of the ratio of calibration interval times). The comparison of the multi-cycle data to the single-cycle data as described above is the primary technique used to validate the standard assumption of moderate time dependency. From Section 4.11 of OSC-9719, if the assumption of moderate time dependency is validated, the drift uncertainty for the extended calibration interval of 30 months is extrapolated by using the square root of the ratio of the average multi-cycle data calibration interval and the average single-cycle data calibration interval: 0 5 ADERANDOM = ADRANDOM X (CIEl CIo) Where: ADERANDOM - random drift term for the extended calibration interval (30 months) ADRANDOM - random drift term calculated from the observed data (18 months) CIE - extended calibration interval (surveillance interval + 25%) or 30 months Clo - averaged calibration time interval from the sample data
- Duke Energy Response to NRC Request for Additional Information April 28, 2011 Page 7 If the Analyzed Drift is determined to be strongly time dependent, the following conservative equation is used.
ADERANDOM = ADRANDOM X CIE /C/o Where: CIE - extended calibration interval (surveillance interval + 25%) or 30 months CIo - averaged calibration time interval from the sample data The bias portion of the Analyzed Drift (ADS/AS), if determined to be significant in the drift calculation per the methods described in Section 4.10 of OSC-9719, will always be conservatively treated as being strongly time-dependent and linearly extrapolated as shown below. ADEBIAS = ADBJAS X CIE! Clo Where: ADEBIAS - bias drift term for the extended calibration interval (30 months) ADBIAS - bias drift term determined from Section 4.10 from the observed data (18 months) CIE- extended calibration interval (surveillance interval + 25%) or 30 months CIo - averaged calibration time interval from the sample data
RAI 6
The letter dated February 11, 2011, indicates that engineering evaluations are performed for all out of tolerance (OOT) conditions exceeding notification limits. The letter indicates that the default notification limit is twice the specified procedure setting tolerance or as specified in the calibration procedure for other reasons. Justify the selection of this criterion, especially considering the information provided in RIS 2006-17 or in TSTF-493 for instrument calibration to meet 10 CFR 50.36 requirements. Specifically, clarify how this criteria is related to the as-found and as-left tolerance limits in the setpoint calculations. Duke Energy Response to RAI 6 As previously noted in the response to RAI 2, the calibration tolerance values specified in the uncertainty analyses are appropriately reflected in the associated instrument calibration procedures. As-found calibration tolerances are conservatively set equal to as-left tolerances in instrument calibration procedures. As-left calibration tolerances are determined as described in the response to RAI 2. Notification limits for engineering evaluations of OOT conditions are specified in each instrument calibration procedure. These limits are established to ensure any OOTs exceeding the acceptable limit or as-found limit as determined in the instrument uncertainty calculation are reported to engineering for evaluation. For most applications, the default limit of two times the specified calibration as-left/as-found setting tolerance is conservative relative to the acceptable limit documented in the uncertainty calculation. As noted in the response to RAI 2, for the replacement RPS/ESPS digital system the "as-found" limit from the uncertainty calculations are directly used as the engineering OOT notification limit in the associated instrument calibration procedure in lieu of the default limit of two times.
- Duke Energy Response to NRC Request for Additional Information April 28, 2011 Page 8
RAI 7
Calculation OSC-9771 and many other documents refer to records of Corrective Actions taken to evaluate the effects of the extended cycle Analyzed Drift on the applicable normal uncertainty allowances. These documents also state that the impact on the proposed channel check limit will be evaluated as a result of Corrective Actions. Please provide the findings of these Corrective Actions. Duke Energy Response to RAI 7 Drift calculation OSC-9771 for RPS Reactor Coolant System Pressure resulted in two corrective actions. Corrective action 2 of Problem Investigation Program (PIP) 09-4103 required evaluation of the effects of the Analyzed Drift determined for a 30 month maximum calibration interval in OSC-9771 on uncertainty calculations OSC-4048 and OSC-8828. Revision 6 of OSC-4048 and revision 3 to OSC-8828 have been completed incorporating the Analyzed Drift determined for a maximum 30 month calibration interval. A copy of OSC-8828 and the associated drift calculation (OSC 9771) is provided in Enclosure 2 of this submittal for reviewer information. The methods used in these calculations are typical of those used for other instruments evaluated. Corrective action 3 of PIP 09-4103 required evaluation of the effects of the analyzed drift determined for a worst case 30-month calibration interval in OSC-9771 on the current channel check acceptance criteria in periodic instrument surveillance procedure PT/_/A/0600/001. This procedure has been revised for all three units changing the acceptance criteria for the channel check for Surveillance Requirement (SR) 3.3.1.1 (RPS Instrumentation RC Pressure Narrow Range) to be "within 22 psi'. This revision was completed prior to implementation of 24 month cycles since the acceptance criteria change was in a conservative direction compared to the previous limit of 26 psi. There were 27 specific instrument drift calculations completed to support extension of the various TS instrument calibration SRs within the scope of the 24 month cycle LAR. The results of many of these drift calculations initiated multiple PIP corrective actions to evaluate the effects of the extended cycle Analyzed Drift on uncertainty calculations and procedure tolerances. Therefore, the findings of all of these corrective actions are rather extensive. The findings specific to OSC-9771 identified in this RAI are noted above. The findings of other corrective actions can be supplied as needed. Note that not all of these corrective actions are complete as of this date, but they will be completed prior to implementation of 24 month cycles on each unit as previously committed by Duke Energy in the May 6, 2010 License Amendment Request.
- Duke Energy Response to NRC Request for Additional Information April 28, 2011 Page 9
RAI 8
Calculation OSC-9852 states in Sections 7.1.3, 7.2.3, 7.3.3, 7.4.3, 7.5.3, and 7.6.3 that justifications for the proposed changes will be provided in a later revisions. Please provide update on these Sections. Duke Energy Response to RAI 8 These sections of the calculation were written to support extension of Selected Licensee Commitment (SLC) Surveillance Requirements. This is outside the scope of the NRC review as Duke Energy did not request NRC to approve any changes to SLC SRs.
April 28, 2011 Page 1 Enclosure 2 Duke Energy Documents
- 1. OSC 8828, Rev. 3, Digital RPS RCS Pressure &Temperature Trip Function Uncertainties and Variable Low RCS Pressure Safety Limit
- 2. OSC 9771, Rev. 1, Drift Analysis for the RPS Reactor Coolant (RC) System Pressure
OSC 8828, Rev 3 Digital RPS RCS Pressure &Temperature Trip Function Uncertainties and Variable Low RCS Pressure Safety Limit
FORM 101.3 (R08-04) CERTIFICATION OF ENGINEERING CALCULATION - REVISION LOG Station And Unit Number Oconee Nuclear Station Units_1, 2, & 3 Title Of Calculation Digital RPS RCS Pressure & Temperature Trip Function Uncertainties and Variable Low RCS Pressure Safety Limit Calculation Number OSC-8828 Active Calculation/Analysis Yes E No 0 Calculation Pages (Vol) Supporting Verif. Issue Documentation (Vol) Volumes Odg Chkd Meth. Appr Date Rev. 1,Z 3. No. Revised Deleted Added Revised Deleted Added Deleted Added Date Date "Other, Date 1 1.2 3-37 IVv, v, L - Lv-
,,.,1 ._-,,. 4 a/a- _ _ _
2 to/*7 71afilo ~ ___~ ~~~~~~Wk _ _ _ _ __ I_ B_ I_ __L__zr~ Af, )I41s01
%S,S4, t s + -. I 3 11, 10A Wlit I U"Q l 10-1410 L ~ _ 1-0-.
I Form 101.1 R08-04 CALCULATION CERTIFICATION OF ENGINEERING Station And Unit Number Oconee Nuclear Station Units 1, 2, & 3 Title Of Calculation Digital RPS RCS Pressure &Temperature Trip Function Uncertainties and Variable Low RCS Pressure Safety Limit Calculation Number OSC-8828 Total Original Pages Through 37 Total Supporting Documentation Attachments 0 Total Microfiche Attachments 0 Total Volumes I Active Calculation/Analysis Yes E No 13 Microfiche Attachment List 0] Yes M No If Active, is this a Type I Calculation/Analysis Yes Q No M (See Form 116.1) These engineering Calculations cover QA Condition I Items. In accordance with established procedures, the quality has been assured and I certify that the above Calculation has been Originated, Checked, or Approved as noted below: Originated By R. G. Chow 42-..4* Date 2/j /06 Checked By S. G. Siry bL.) ji Date "AJ)Da Verification Method: Method 1 Method 2 Method 3 L" Other EI Approved By S. B. Thomas Date ZIA-Z,,,ola_ ed To Document Management er- . L/i6'- Date -IL*/oo(e Received By Document Management Date Complete The Spaces Below For Documentation Of Multiple Originators Or Checkers Pages Through Originated By Date Checked By Date Verification Method: Method 1 I] Method 2 [-] Method 3 [] Other E] Pages Through Originated By "_"_Date Checked By Date Verification Method: Method 1 E] Method 2 I Method 3 rI Other r-Pages Through Originated By Date Checked By Date Verification Method: Method 1 EI Method 2 -I Method 3 LI Other LI
Calculation Number OSC-8828 a Form 101.2 (R3-03) REVISION DOCUMENTATION SHEET Revision Number Revision Descrption 0 Original Issue Revised the calculation in its entirety to incorporate new calibration procedures and the new Weed temperature transmitter. In addition, as found calibration tolerances were determined in this calculation. 2 Revised the calculation to incorporate comments from AREVA and also to incorporate new TXS specifications. 3 Revised the calculation to incorporate results of 24 month drift study contained in OSC-9771 and removed uncertainty calculations for re-calibration of RCS NR pressure indication for low-range use. I
Compact Disc Archival List Calculation File Number: OSC-8828 Revision Disc Volume Archival Directory Checker Initials Number Number & Date 0 NE0116 /salosc8828/revOa F 17-q Is,,/cRI'StIravI X:ý 7/
- 2. Ne 0133 ISl/ae 8l7* e*7- ..
3 Wfo I /S3 ,4/0hc f,,Yrw 10k ho Page i FormNE-116.1 Revision5
(From Attachment A of Oconee EM - 4.9, Revision 3) CALCULATION IMPACT ASSESSMENT (CIA) Station / Unit ONS / 1, 2, 3 Calculation No. OSC-8828 Rev. 0 Page PIP No. (if applicable) N/A By QG how* Date 2 Prob. No. (stress & s/r use only) N/A Checked By S.G. Sir, Date ,21!L0 NEDL reviewed to identify calculation? YES NO (formally SAROS) Identify in the blocks below, the groups consulted for an Impact Assessment of this calculation origination/revision. Indiv. Contacted/Date Indiv. Contacted/Date L) RES NGO R. G. Chow [Power, I & C, ERRT, [QA Tech. Services (ISI), Reactor] Severe Accident Analysis, Elect. Sys. & Equip., Design
& Reactor Supp., Civil Structural, Core Mech. &
T/H Analysis, Mech. Sys. & LI MCE __________ Equip., Nuclear Design, __________ [Primary Systems, Balance Ety Naly sisnd of Plant, Rotating Equipment, Safety Analysis, and Valves & Heat Exchangers, Matls/Metallurgy/Piping] Civil] LI MOD [Mechanical Engr., Electrical Engr., Civil Engr.] U Training Q LocalIT Li Operations - OPS Support [ Regulatory Compliance [ Maintenance - Tech. Support Q Chemistry QJ Work Control - Program. Supp. L1 Radiation Protection Q] Other Group Q No Group required to be consulted Listed below are the identified documents (ex: TECHNICAL SPECIFICATION SECTIONS, UFSAR SECTIONS, DESIGN BASIS DOCUMENTS, STATION PROCEDURES*, DRAWINGS, OTHER CALCULATIONS, ETC.) that may require revision as a result of the calculation origination or revision, the document owner/group and the change required (including any necessary PIP Corrective Actions).
*Note: Any design changes, which requirechanges to Station Procedures,must be transmittedas Design Deliverable Documents.
This calculation revises OSC-4048 as each unit incorporates the Digital RPS from AREVA. A search was performed based on Calculation OSC-4048. DOCUMENT GROUP CHANGE REOUIRED OSC-6982 CEN To be tracked by Digital RPS Replacement Project OSC-5844, OSC-8603, OSC-8629 OSC-8717 MTH No Change Required OSC-4375, OSC-4378, OSC-4386, OSC-5123, OSC-5233, OSC-5827, OSC-6554, OSC-7362, OSC-7572, 6 OSC-7573, OSC-8022, OSC-8024, OSC-8117, OSC-8126 NEA To be tracked by Digital RPS Replacement Project (Attach Additional Sheets As Required)
(From Attachment A of Oconee EM - 4.9. Revision 3)
,.MEW CALCULATION IMPACT ASSESSMENT (CIA)
L Station / Unit PIP No. (if applicable) ONS / 1, 2,3 Prob. No. (stress & s/r use only) N/A N/A Calculation No. OSC-8828 By R.G. Chow Checked By S.G. Siry Rev. Date Date 0 Page iii DOCUMENT GROUP CHANGE REOUIRED OSC-8471, OSC-8609, OSC-8684 NEA No Change Required
.OSC-4707 OND To be tracked by Digital RPS Replacement Project OSC-6128, OSC-7940, OSC-8178, OSC-8202, OSC-8413, OSC-8526, OSC-8625, OSC-8630, OSC-8658, OSC-8707 OND No Change Required OSC-8010 MOD No Change Required OSC-8108 MOD No Change Required OSC-8623 MOD No Change Required 4
6I (Attach Additional Sheets As Required)
(From At achment A of Oconee Eli - 4.9, Revision 9) ACALC *ULATION IMPACT ASSESSMENT (CIA) 9 Station / Unit PIP No. (if applicable) ONS / 1, 2, 3 Prob. No. (stress & s/r use only) N/A N/A Calculation No. OSC-8828 By R.G. Chow~a7 Checked By S.G. Siry Rev. Date Date I A-,/o. Page iv INote: a NEDL search is NOT required for NEDL reviewed to identify calculation? L YES i NO I calculation origination (i.e., Rev. O's) Identify in the blocks below, the groups consulted for an Impact Assessment of this calculation origination/revision. lndiv. Contacted/Date Indiv. Contacted/Date L RES NGO R. G. Chow [Power, I & C, ERRT, U [QA Tech. Services (ISI), Reactor] Severe Accident Analysis, Elect. Sys. & Equip., Design
& Reactor Supp., Civil Structural, Core Mech. &
T11 Analysis, Mech. Sys. & Lj MCE Equip., Nuclear Design, [Primary Systems, Balance Safety Analysis, and of Plant, Rotating Equipment, Matls/Metallurgy/Piping] Valves & Heat Exchangers, Civil] Ll MOD [Mechanical Engr., Electrical Engr., Civil Engr.] Ll Training 0 ji Operations - OPS Support 03Local IT Li Regulatory Compliance ['L Maintenance - Tech. Support Ll Chemistry L) Work Control - Program. Supp. Ll Radiation Protection L3 Other Group Qi No Group required to be consulted Listed below are the identified documents (ex: TECHNICAL SPECIFICATION SECTIONS, UFSAR SECTIONS, DESIGN BASIS DOCUMENTS, STATION PROCEDURES*, DRAWINGS, OTHER CALCULATIONS, ETC.) that may require revision as a result of the calculation origination or revision, the document owner/group and the change required (including any necessary PIP Corrective Actions).
*Note: Any design changes, which require changes to Station Procedures,must be transmittedas Design Deliverable Documents.
DOCUMENT GROUP CHANGE REQUIRED OSC-6982 CEN To be tracked by Digital RPS Replacement Project OSC-5844, OSC-8603, OSC-8629 OSC-8717 MTH No Change Required OSC-4375, OSC-4378, OSC-4386, OSC-5123, OSC-5233, OSC-5827, OSC-6554, OSC-7362, OSC-7572, OSC-7573, OSC-8022, OSC-8024, OSC-8117, OSC-8126 NEA To be tracked by Digital RPS Replacement Project s (Attach Additional Sheets As Required)
(From Attachment A of Oconee EM - 4.9. Revision 3) CALCULATION IMPACT ASSESSMENT (CIA) m U PStation / Unit PIP No. (if applicable) ONS / 1, 2,3 Prob. No. (stress & sir use only) N/A N/A Calculation No. OSC-8828 By R.G. Chow Checked By S.G. Siry 11 Rev. Date Date I Page DOCUMENT GROUP CHANGE REQUIRED OSC-4707 OND To be tracked by Digital RPS Replacement Project OSC-8010 MOD No Change Required OSC-8108 MOD No Change Required OSC-8623 MOD No Change Required OSC-8623 MOD No Change Required OSC-8695 MOD No Change Required I (Attach Additional Sheets As Required)
(From Attachment A of Oconee EM - 4.9. Revision 9)
ý1 CALCULATION IMPACT ASSESSMENT (CIA) a Station / Unit PIP No. (if applicable)
ONS / 1, 2,3 Prob. No. (stress & s/r use only) N/A N/A Calculation No. OSC-8828 By R. G. Chow Vdh&- Checked By S.G.Siry Rev. Date 2 ZJr./os Date 2/1Sa"[(g Page vi Note: a NEDL search is NOT required for NEDL reviewed to identify calculation? El YES El NO calculation origination (i.e., Rev. O's) Identify in the blocks below, the groups consulted for an Impact Assessment of this calculation origination/revision. Indiv. Contacted/Date ]ndiv. Contacted/Date ElRES
- NGO R. G. Chow
[Power, I & C, ERRT, [QA Tech. Services (ISI), Reactor] Severe Accident Analysis, Elect. Sys. & Equip., Design
& Reactor Supp., Civil Structural, Core Mech. &
T/H Analysis, Mech. Sys. & MCE Equip., Nuclear Design, [Primary Systems, Balance Safety Analysis, and of Plant, Rotating Equipment, Matls/Metallurgy/Piping] Valves & Heat Exchangers, Civil] [-1MOD [Mechanical Engr., Electrical Engr., Civil Engr.] El Training Q] Local IT 0 L3 Operations - OPS Support El Regulatory Compliance [' Maintenance - Tech. Support El Chemistry L3 Work Control - Program. Supp. EL Radiation Protection l3 Other Group El No Group required to be consulted Listed below are the identified documents (ex: TECHNICAL SPECIFICATION SECTIONS, UFSAR SECTIONS, DESIGN BASIS DOCUMENTS, STATION PROCEDURES*, DRAWINGS, OTHER CALCULATIONS, ETC.) that may require revision as a result of the calculation origination or revision, the document owner/group and the change required (including any necessary PIP Corrective Actions).
*Note: Any design changes, which require changes to Station Procedures,must be transmittedas DesignDeliverable Documents.
DOCUMENT GROUP CHANGE REQUIRED OSC-6982 CEN To be tracked bv Digital RPS Reolacement Proiect OSC-5844, OSC-8603, OSC-8629 OSC-8717 MTH No Change Required OSC-4375, OSC-4378, OSC-4386, OSC-5123, OSC-5233, OSC-5827, OSC-6554, OSC-7362, OSC-7572, OSC-7573, OSC-8022, OSC-8024, OSC-8117, OSC-8126 NEA To be tracked by Digital RPS Replacement Project 0 (Attach Additional Sheets As Required)
~Frnm Attmu~hr~wnI A oCOconee EM -4 Q Revision 3~
m CALCULATION IMPACT ASSESSMENT (CIA) Station / Unit ONS / 1, 2,3 Calculation No. OSC-8828 Rev. 2 Page vii a PIP No. (if applicable) Prob. No. (stress & s/r use only) N/A N/A By R. G. Chow Ik2&--_ Checked By S.G. Siry Yb xq-Date Date tLtL& DOCUMENT GROUP CHANGE REQUIRED OSC-4707 OND To be tracked by Digital RPS Replacement Project OSC-8010 MOD No Change Required OSC-8108 MOD No Change Required OSC-8623 MOD \ No Change Required OSC-8623 MOD No Change Required OSC-8695 MOD No Change Required 6 (Attach Additional Sheets As Required) S
(From Attachment A of Oconee EM - 4.9. Revision 9) CALCULATION IMPACT ASSESSMENT (CIA) Station/ unit Rev. 3 Page viii dI PIP No. (if applicable) ONS / 1, 2, 3 Prob. No. (stress & s/r use only) N/A N/A Calculation No. OSC-8828 Checked By By M.E. Carroll
. Note:baýNED Date 7/26/10 Date serc l/0 i NT eqirdo NEDLrevewe toidetifycalulaion YE NO Note: a NEDL search is NOT required forI NEDI reviewed to identify calculation? [ YES [' NO calculation origination (i.e., Rev. O's)
Identify in the blocks below, the groups consulted for an Impact Assessment of this calculation origination/revision. lndiv. Contacted/Date Indiv. Contacted/Date Lj RES [l NGO [Power, I & C, ERRT, [QA Tech. Services (ISI), Reactor) Severe Accident Analysis, Elect. Sys. & Equip., Design
& Reactor Supp., Civil Structural, Core Mech. &
[ MCE T/H Analysis, Equip., NuclearMech. Sys. & Design, __________ [Primary Systems, Balance Ety Naly sis , Safety Analysis, and of Plant, Rotating Equipment, Valves & Heat Matls/Metallurgy/Piping] Exchangers, Civil] L- MOD [Mechanical Engr., Electrical Engr., Civil li Training Engr.] I0 - Operations - OPS Support L3 Local IT Li Regulatory Compliance El Maintenance Support
- Tech.
U Chemistry El Work Control - Program. Supp. U3Radiation Protection Lj Other Group IZINo Group required to be consulted Listed below are the identified documents (ex: TECHNICAL SPECIFICATION SECTIONS, UFSAR SECTIONS, DESIGN BASIS DOCUMENTS, STATION PROCEDURES*, DRAWINGS, OTHER CALCULATIONS, ETC.) that may require revision as a result of the calculation origination or revision, the document owner/group and the change required (including any necessary PIP Corrective Actions).
*Note:Any design changes, which requirechanges to Station Procedures,must be transmittedas Design Deliverable Documents.
DOCUMENT GROUP CHANGE REQUIRED OSC-8610 MCE To be tracked by PIP-0 10-07500 OSC-8612 MCE To be tracked by PIP-O-10-07500 OSC-8695 MCE To be tracked by PIP-O-10-07500 (Attach Additional Sheets As Required)
NUCLEAR ENGINEERING DIVISION ENGINEERING CALCULATION PROCEDURE APPLICABILITY CHECKLIST 0 Description of Analysis The purpose of this calculation is to determine the total loop uncertainty (TLU), per EDM-102 (Reference 5.A.a) guidance, associated with the Reactor Coolant System (RCS) variable low pressure, low pressure, high pressure, and high temperature trip functions in support of the Oconee Digital Reactor Protection System Replacement Project. In addition, this calculation is to determine the revised safety limit for the variable low pressure trip function. This analysis is QA Condition 1. S Determination of QA Condition I Applicability YES NO
*[ Does this analysis justify a change in a Technical Specification/COLR limit or verify the acceptability of a current Technical Specification/COLR limit?
-1
- Does this analysis justify a design or a change in the performance or design of safety-related structures, systems, or components?
-J
- Does this analysis modify or justify the licensing basis safety analysis?
*
- Is this analysis intended to provide the basis for, or input to, other safety-related analyses?
If the answer to any of the above questions is yes, then this analysis is safety-related and must be classified as a QA Condition 1 item. As such it must satisfy the requirements of NE-103 and EDM-101. OSC-8828 Rev. 0 Page 1 RGC 02/01/2006 Form NE-103.1 Revision 9
NUCLEAR ENGINEERING DIVISION ENGINEERING CALCULATION REVIEW CHECKLIST 0 YES NOT NOT APPLICABLE TO BE COMPLETED BY REVIEWER A description of the analysis has been entered on Form NE-103.J. U The QA Condition of the calculation has been determined on Form a NE-103.1 and entered on Form EDM-101. 1. Design methods and procedures have been referenced. U U Design criteria have been identified. 19 U Input data and assumptions are valid and properly documented. a All computer programs are properly identified, documented, and executed consistently with their derivation. E All computer programs have been certified in accordance with NSD-800 as appropriate. Calculation and analytical methodologies are consistent with approved methodologies and numerical results have been verified. a Q All hand calculations have been verified. Conclusions and results are consistent with the calculations. a 11 The required Reactivity Management section (per NSD-304) has been included and the reviewer agrees with its contents and conclusions. UFSAR markups have been documented. U Current revision of generic REDSAR was used. Revisions to generic REDSAR reference values, resulting from this Yes i No Li calculation, have been documented and communicated appropriately. TO BE COMPLETED BY APPROVER Is cross disciplina reviy ICD*.*,ired? Signature _ _,t_ _,__v_ CDR by: wte 9,0-4,4 Date: a t-is.
/IL I
Original Reviewed by: kflm~L~1~ ~ A " il-- y J). a Rev. _Reviewed by: CDR by: _ Date: 7k:0Q7 Rev. 2 Reviewed by: ~Q~fl4U CDR by: #4//w Date: 21a5f02 Rev. __ Reviewed by: CDR by: Date:. OSC-8828 Rev. 0 Page 2 RGC 02/01/2006 Form NE-103.2 Revision 9
Calculation Number OSC-8828 Revision 3 Engineering Calculation Review Checklist 0 A separate checklist should be used for the original and each revision To be Completed by the Reviewer Not Yes Applicable 0 The QA Condition of the calculation has been determined and entered on Form EDM-101.1 o 99 A pre-analysis or design review meeting was held to discuss the analysis approach and gain stake holder support o All computer codes have been properly identified, documented, and executed consistently with their derivations o All computer codes have been certified in accordance with NSD-800 as appropriate or a single use application has been verified within the calculation
. " Design criteria have been identified X] 0 Calculation and analytical methodologies are consistent with approved methodologies A clear link to any applicable NRC approved methodology has been included. For newer calculations (>1998) this should be included in a Methodology section.
The required Reactivity Management section (per NSD-304) has been included a 3 *UFSAR markups have been documented 0 REDSAR markups have been documented SAIM markups have been documented To Be Completed by the Aeprover Yes No 0Originator and Reviewer of this revision are qualified per NE-107 to perform the [_ analyses or a qualified mentor was assigned and signed as a co-preparer oI
- Has a post analysis critique or lessons learned discussion been scheduled to discuss the outcome of this calculation or analysis?
1o
- IsCross Disciplinary Review (CDR) required?
If Yes, what group(s) should perform the CDR Q+A 0 Reviewed by: Date /0,/A0 . Approved by: Date NED Engineering Calculation Review Form - 02/26/2010 Page 2a
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties TABLE OF CONTENTS
- 1. STATEMENT OF PROBLEM / PURPOSE 4 1.1 Purpose 1.2 Analyzed Loop Function 1.3 Plant Condition Requiring Operation 1.4 Location and Applicable Environment
- 2. RELATION TO QA CONDITION / NUCLEAR SAFETY 7
- 3. DESIGN CALCULATION METHOD 8 3.1 Uncertainty Determination 3.2 Graded Approach Calculations 3.3 Single Sided Setpoints and 2o Reduction
- 4. UFSAR / TECHNICAL SPECIFICATION APPLICABILITY 9
- 5. REFERENCES 10
- 6. ASSUMPTIONS / DESIGN INPUT 12 6.1 Assumptions 6.2 Design Input/Bases 6.3 Comments
- 7. CALCULATION 13 7.1 Instrument Block Diagram 7.2 Constants and Unit Conversions 7.3 Device/Loop Uncertainty Term Identification 7.4 Initial Condition Uncertainty Determination 7.5 Total Loop Uncertainty Determination 7.6 Rack Uncertainty 7.7 Core Exit to Hot Leg Tap Pressure Drop 7.8 Variable Low RCS Pressure Safety Limit 7.9 Setpoint Analysis 7.10 Loop Scaling 7.11 As-Found Tolerance Determination
- 8. MAINTENANCE CALIBRATION REQUIREMENTS 38
- 9. REACTIVITY MANAGEMENT 38
- 10. CONCLUSIONS 38 APPENDIX A REDSAR Markups 40 0,
OSC-8828, Rev 2 Page 3 RGC 02/25/2008
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties . 1. Statement of Problem / Purpose 1.1 Purpose The purpose of this calculation is to determine the total loop uncertainty (TLU), per EDM-102 (Reference 5.A.a) guidance, associated with the Reactor Coolant System (RCS) variable low pressure, low pressure, high pressure, and high temperature trip functions in support of the Oconee Digital Reactor Protection System Replacement Project. In addition, this calculation is to determine the revised safety limit for the variable low pressure trip function. This analysis is QA Condition 1. Four narrow range RCS pressure channels are used to develop the high RCS pressure, low RCS pressure, and the variable low RCS pressure reactor trips. They are listed below: RCPT0017P (RC3A-PTl) RCPT00I 8P (RC3A-PT2) RCPT0019P (RC3B-PT1) RCPT0020P (RC3B-PT2) Four RCS outlet temperature channels are used to develop the variable low RCS pressure and the high RCS outlet temperature reactor trips as listed below: RCRDOOOIA (RC4A-TEI) RCRD0002B (RC4A-TE4) RCRD0003A (RC4B-TE I) RCRD0004B (RC4B-TE4) Each of these channels includes the pressure transmitter (or temperature RTD and transmitter) to the Framatome TELEPERM XS (TXS) digital processor modules. This calculation documents the acceptability of the uncertainty assumptions and identifies specific calibration requirements which were utilized as input for the loop uncertainty determination. 1.2 Analyzed Loop Function The variable low RCS pressure trip function provides protection against exceeding steady state DNB safety limit. This protection is provided by monitoring RCS pressure and temperature conditions and tripping the reactor when the equivalent core exit pressure and temperature are near a DNB limit. The current Technical Specification setpoint for this trip is defined in the Core Operating Limits Report (COLR) as follows (Reference 5.G ): P_setpoint := 11.14 x T hot - 4706 where, P setpoint = hot leg pressure setpoint (psig) T hot = hot leg temperature (fF) OSC-8828, Rev I Page 4 RGC 07/20/2007
Oconee Nuclear Station Units 1,2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties When the RCS pressure decreases below a value that is permitted at a given RCS temperature, a reactor trip is generated. In a similar manner, if RCS hot leg temperature increases to a value above that permitted at a given RCS pressure, a reactor trip is generated. This is demonstrated in Figure 1-1, a diagram of the variable low RCS pressure trip instrumentation channel. The trip setpoint is determined by adjusting the variable low pressure safety limit by an allowance to account for instrument uncertainty and the pressure difference between the core outlet and the hot leg pressure tap. This differential pressure adjustment is calculated as a function of core outlet pressure. Variable low pressure safety limits are calculated for both 4 and 3 pump operation. The pump combination that produces the limiting hot leg temperatures as a function of hot leg pressure is used to determine the RPS variable low pressure setpoint. From Reference 5.F.b, the low RCS pressure trip shall provide protection against DNB during steady state and transient operation. The trip setpoint is determined by adjusting the value assumed in the safety analyses by an allowance to account for instrument uncertainty and pressure difference between tap location. By tripping the reactor, the low RCS pressure trip reduces the energy addition to the reactor building during certain events. Reduced energy addition to the reactor building will help maintain the reactor building pressure below the design pressure (59 psig). From Reference 5.F.b, the high RCS pressure trip sets the maximum pressure at which the reactor is allowed to operate. The high RCS pressure trip shall provide protection for the RCS high pressure safety limit defined by design criteria for Class I pressure vessels by American Society of Mechanical Engineers (ASME) code. This protection is provided through monitoring RCS pressure and initiating a reactor trip when RCS pressure exceeds the trip setpoint. By initiating a reactor trip during increasing RCS pressure events, this trip provides direct protection for the RCS boundary as well as indirect protection for fuel cladding and the reactor building. The trip setpoint is determined by adjusting the trip value assumed in the safety analyses by an allowance to account for instrument uncertainty and pressure difference between tap location. This trip function, in conjunction with the pressurizer safety valves, assures that the RCS pressure safety limit will not be exceeded during an overpressure event. From Reference 5.F.b, the high reactor coolant temperature trip sets the maximum RCS outlet temperature at which the reactor is allowed to operate. The high Reactor Coolant System outlet temperature trip shall provide protection against exceeding steady state and transient DNB limits. This protection is provided through monitoring RCS hot leg temperatures and initiating a reactor trip when RCS hot leg temperature exceeds the trip setpoint. The trip setpoint is determined by adjusting the high temperature safety limit by an allowance to account for instrument uncertainty. This calculation is divided into three parts. First, the total instrument loop uncertainty for the RCS variable low pressure, low pressure, high pressure, and high temperature trip functions are determined. Next, the allowance for the pressure difference between the core exit and and hot leg taps are documented. Finally, the revised safety limits are determined by adjusting the variable low pressure setpoint by an allowance for instrument uncertainty and the pressure difference between the exit and hot leg taps. S OSC-8828, Rev I Page 5 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties Hieh Temnerature Trio 0* C-) RCS HOT LEG TEMPERATURE Figure 1-1. Reactor Coolant System Pressure-Temperature Envelope is OSC-8828, Rev 1 Page 6 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 1.3 Plant Conditions Requiring Operation The RCS variable low pressure, low pressure, high pressure, and high temperature trip functions are considered safety-related loop and credited in the safety analyses. Per Reference 4.2 Table 3.3.1-1 these trip function are applicable in Modes I and 2. The use of these trip functions are not required to mitigate accidents which causes harsh enviroments in the area of the sensing device; therefore, only normal uncertainties are calculated. Duc te the Recezity Of ancthfr low range (0 600 psig) RS pressure indicaticn, one eoAfhe noaow .ange 'I
..... u. t.n...itr--
. (,RCPT00!9P Unit *1, 1RCPT-001 -2, RCIT-0I171:
Unt 2. and Un 3) iS Fe alibr-at: to the low range (Referenco
. .D..). This rc-
.alibr.ti.n typeally is performed when the RCS has depressur-ized tc less than 17-00 psig.
1.4. Location and Applicable Environment 1.4.1 Pressure Transmitters The RCS pressure transmitters are located inside the Reactor Building between Elevations 828' and 832' (Reference 5.C). From Reference 5.H the environmental conditions are as follows: Environmental Condition Temperature Pressure Radiation Normal 60"F - 120OF 0psig - 5 psig 3.0E4 tad (40 year dose) 1.4.2 Temperature RTDs The RCS temperature RTDs are located inside the Reactor Building at Elevations 844'-8" (Reference 5.C). From Reference 5.H the environmental conditions are as follows: Environmental Condition ITemperature Pressure Radiation Normal 60'F - 120*F 0 psig - 5 psig 3.0E7 rad (40 year dose) 1.4.3 TXS Digital Processor The Framatome TELEPERM XS (TXS) digital processor modules will be located within the existing protection cabinets which are located in the Control Complex. This is a controlled environment which specifies temperature to vary between 74'F to 80'F (Reference 5.1-1). This area is not subject to accident induced radiation or pipe rupture environments.
- 2. Relation to QA Condition / Nuclear Safety This calculation is a QA Condition I because the subject instrumentation uncertainties are used in safety related calculations.
OSC-8828, Rev 3 Page 7 MEC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature I Trip Function Uncertainties
- 3. Design Calculation Method 3.1 Uncertainty Determination The methodology employed by this calculation is based on Reference 5.A.a and 5.A.b. The methodology accounts for random-independent (x,y), random-dependent (w,u) and non-random/biases (v, t) uncertainty terms differently in determining the total loop accuracy (TLU), as follows:
+TLU = +{x2 + y 2 + (w + u)2}lr1 + v + t IEQUATION 3-11 2
-TLU=-{x2+y +(w+u)2)1}2 -v-t Typical uncertainty terms and terminology follows:
Uncertainty Terms: A - Device/rack Accuracy. PMA - Process measurement allowance. CL - Current leakage. PSE - Device power supply effect. CTE - Calibration tolerance. R - Radiation Effects D - Device drift. RES - Resolution/readability. EA - Environmental allowance SA - Seismic allowance. MTE - Measuring & test equipment SPE - Static pressure effects. PEA - Primary element allowance TE - Device/rack temperature effect. CE - Calibration Effects DB - Deadband. (including M&TE and CTE) S Terminology/Abbreviations: AL - Analytical Limit. PL - Process Limit. AV - Allowable Value. SP - Nominal Set Point. OL - Operating Limit. SL - Safety Limit. All errors are defined with the following sign convention: Error = Indication - Actual. Thus, positive errors make the instruments read or output a higher than actual value and negative errors make the instruments read or output a lower than actual value. For example, if a pressure of 700 psia were to be measured by a pressure transmitter which had an error of + 1.0% of reading, then the pressure transmitter would output the equivalent of 707 psia. 3.2 Graded Approach Calculations A graded approach is not used in this calculation. This calculation uses a very rigorous approach. OSC-8828, Rev I Page 8 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 3.3 Single Sided Setpoints and 2y Reduction If a setpoint application or operating restriction is always approached from one direction and functions to ensure that a single value (i.e. analytical or process limit) is not exceeded, then a statistical reduction factor can be applied .. to a loop uncertainty value which is based on a 2cr symmetric (normal) distribution (Reference 5.A.a). The 95% confidence interval would be unchanged, since the probability distribution curve is effectively shifted slightly to one side of the analytical/process limit. For a normal distribution, a 95% confidence interval can be obtained with 2.5% of the population falling on either side (outside) +/-1.96 a, or with 5% falling outside of+1.645 cr (or -1.645 d depending on the direction of interest). Therefore, for setpoints approached from one direction, a reduction factor of 1.645/1.96 = 0.84 can be applied to the random-independent portion of the over-all loop uncertainty value. a reduction :=.0.84
- 4. UFSAR / Technical Specification Applicability 4.1. Oconee Nuclear Station Units 1, 2, & 3 UFSAR Chapters 6, 7, and 15 4.2 Oconee Nuclear Station Units 1, 2, & 3 Technical Specifications Section 3.3.1 and 3.3.2, Amendments 355, 357, & 356, respectively OSC-8828, Rev 2 Page 9 RGC 02/25/2008
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties O 5. References A. a) EDM-102: Instrument SetpointfUnccrtainty Calculations, Rev. 3, 02/25/05 b) ISA-S67.04, Part II, Setpoints for Nuclear Safety Related Instrumentation, January 2000 B. a) OM-201.N-0001.001, Oconee Nuclear Station TXS RPSIESPS Replacement System Cabinet Design: 1PPSCA0001', AREVA Document No. 38-5069817-05, Rev. 5 b) OM-201.N-0003.001, Oconee Nuclear Station TXS RPS/ESPS Replacement System Cabinet Design: IPPSCA0003, AREVA Document No. 38-5069819-05, Rev. 5 c) OM-201.N-0005.001, Oconee Nuclear Station TXS RPS/ESPS Replacement System Cabinet Design: IPPSCA0005, AREVA Document No. 38-5069821-06, Rev. 6 d) OM-201.N-0007.001, Oconee Nuclear Station TXS RPS/ESPS Replacement System Cabinet Design: IPPSCA0007, AREVA Document No. 38-5069823-05, Rev. 5 e) OM-201.N-0024.005, Oconee Nuclear Station, Unit 1 RPS/ESF Controls Upgrade Software Design Description, AREVA Document No. 51-5065423-07, Rev. 7 C. a) Drawings for RCS Pressure Transmitter Drawing 0-422-AA-3, Instrument Layout Location Plan Intermediate Floor (U 1) EL 825'-0", Rev. 21 Drawing O-1422-AA-3, Instrument Layout Location Plan Intermediate Floor (U2) EL 825'-0", Rev. 20 Drawing 0-2422-AA-3, Instrument Layout Location Plan Intermediate Floor (U3) EL 825'-0", Rev. 11 b) Drawings for RCS Temperature RTD Drawing 0-887, Conduit and Tray Operating Floor (UI1) EL. 844'-6", Rev. 12 Drawing 0-1887, Conduit and Tray Operating Floor (U2) EL. 844'-6", Rev. 18 Drawing 0-2887, Conduit and Tray Operating Floor (U3) EL. 844'-6", Rev. 11 D. a) IP/0/A/0315/015 A, TXS Channel A Analog/Digital Input Module Calibration and Functional Test, Rev. 0 (Draft) b) IP/0/A/0315/031, TXS RPS RC Pressure Transmitter Calibration, Rev. 0 (Draft) c) IP/O/A/0315/010, TXS RPS RC Temperature Transmitter Calibration, Rev. 0 (Draft) d) ....... . RC"v . . . npest~e
. -2tiinite Rff-lge, Change fer-LTOP
........... o :kFr E. Oconee EDB - Equipment Data Base on Passport version 10 F. a) OSS-0254.00-00-1033, "Design Basis Specification for Reactor Coolant System," Rev. 25 b) OSS-0254.00-00-2002, "Design Basis Specifiation for the Reactor Protective System," Rev. 11 c) OSS-0254.00-00-2001, "Design Basis Specification for the ATWS Mitigation System Actuation Circuitry (AMSAC) and the Diverse Scram System (DSS)," Rev. 11 G. Oconee Core Operating Limit Report (COLR), for 01C24, 02C22, and 03C23 H. EQCM, "Oconee Nuclear Station Environmental Qualification Criteria Manual," Rev. 19 I. DPC-1210.04-00-0005, "Measuring and Test Equipment (M&TE) Uncertainties," Rev. 3 9
OSC-8828, Rev\ ' Page 10 RGC 02/25/2008
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties J. OM-267-0968-001, Rosemount Model.! 154 Alphaline Nuclear Pressure Transmitter, Rev. 4 K. a) Weed Model N9031-1A RTD OM-267-1337-00 1, Rev. I, Vendor Number 0337-333533-001 Sheet I OM-267-1337-003, Rev. D2, Vendor Number 0337-333533-001 Sheet 3 OM-267-1336-00 1, Rev. D2, Installation/Instruction/Operation Manual for N903 I-IA RTD and Associated Equipment b) Weed Model N7014 Temperature Transmitter AREVA Document No. 01-9022869-000, N7014 Temperature Transmitter Installation/Instruction/Operation Manual L. a) AREVA Document No. 51-9004194-000, Clarification of Accuracy Specification for TELEPERM XS Modules SAA 1,SNV I, and S466, dated October 14, 2005 b) AREVA Document No. 01-1007767-01, TELEPERM XS SAAI Analog Signal Module (6FK5248-8AA) Copyright 2004 c) AREVA Document No. 01-1007763-01, TELEPERM XS S466 Analog Input Module (6FK5221-8BA), Copyright 2004 M. Calculation OSC-2729, "Oconee Nuclear Station RETRAN Transient Analysis Model," Rev. 12 (SA #249) N. B&W Document No. 32-1125233-00, RCS Pressure Drop, Core Outlet to Hot Leg Pressure Tap, ONS-3, April 13, 1981.
- 0. Calculation OSC-8623, "RPS & ESFAS System Functional Description for Oconee Nuclear Station Unit I for AREVA TELEPERM XS," Rev. 5 P. Calculation OSC-6221, "FSAR Section 15.2 - Startup Accident," Rev. 4 (SA #742)
Q. OSC-9771, Rev. 0, "Drift Analysis for RPS Reactor Coolant (RC) System Pressure (TS SR 3.3.1.5)," Jan. 2010. OSC-8828, Rev 3 Page I I MEC 07/26/2010
~Oconee NuclearPressure Digital RPS Trip RCS Station Units 1, 2, & 3]
& Temperature Function Uncertainties
- 6. Assumptions / Design Inputs 6.1 Assumptions 6.1.1 Calibrations of the subject loops are assumed to be performed every 24 months with an allowable 25%
grace period (6 months). 6.1.2 Resolution and drift may be assumed equal in magnitude to the reference accuracy if not given in the instrument's specifications. This is a standard assumption per Reference 5.A. 6.1.3 The maximum AC and DC loop power supply variations are assumed to be within +/- 10% and +/-5% of nominal, respectively. This is a standard assumption from Reference 5.A 6.1.4 For the purpose of this calculation to support the implementation of the Replacement Digital Reactor Protection System, the measurement and test equipment are taken out of draft calibration procedures (Reference 5.D). Calibration tolerances for all the equipment are determined within this calculation for incorporation into the draft procedures. 6.1.5 For the purpose of this calculation the temperature within the TXS protection cabinets is assumed to increase by an additional 201F. 6.1.6 Reference 5.L states that the SAA1 reference accuracy is 0% span (to bounded by the temperature effect). For the purpose of calibration tolerance effect only, the reference accuracy of SAAl is assumed to be equal to the resistor tolerance which is assumed to be 0.05% span. 6.2 Design Input/Bases Pressure transmitter uncertainties are obtained from OM-267-0968-001 (Reference 5.J). RTD and RTD transmitter uncertainties are obtained from Reference 5.K. TXS TELEPERM instrument module uncertainties are obtained from Reference 5.L. Measurement and test equipment are obtained from Calculation DPC- 1210.04-00-0005 (Reference 5.1). 6.3 Comments None OSC-8828, Rev I Page 12 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties . 7.0 Calculation 7.1 Instrument Block Diagram ICs (not calculated in this analysis) TXS Digital Processor Ouput Not Used TXS Digital processor output Figure 7-1. (Reference 5.B) 7.2 Constants and Unit Conversions OF R
°C -OF psig - psi psia -opsi
".1 ruth :=- yr 12 V - volt
/
OSC-8828, Rev I Page 13 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 7.3 Device/Loop Uncertainty Term Identification The high and low RCS pressure instrumentation loops consist of a pressure transmitter, SAA1 analog signal module, and S466 analog input module. The high RCS temperature instrumentation loop consists of a RTD, RTD transmitter, SAAI analog signal module, and S466 analog input module. This portion of the calculation will be divided into two sections for each uncertainty component. Each component will have its individual uncertainty terms identified and documented. Then the individual uncertainty terms will be statistically combined to determine the module (or module grouping) uncertainty terms. The module uncertainty terms will be calculated for each environmental condition for which it is required to function. Finally, the module uncertainty terms are statistically combined in Sections 7.4 and 7.5 to determine the initial conditions and the TLUs for each string, respectively. 7.3.1 Pressure Transmitter All uncertainties in this section are for a Rosemount Model I I54GP9RB (Reference 5.E) pressure transmitter. From References 5.D and 5.E, the input and output ranges of the transmitter for each unit are: Modes 1-2 input: 1700 to 2500 psig output: 4 to 20 mADC LTOP Condiefr.l inpstts 0 te600psig eutpk4 te 20 mADC-All uncertainties given below are random-independent terms unless stated otherwise. A - Pressure Transmitter Accuracy (random independent) Specified as = +/-0.25% of calibrated span (Reference 5.J). Includes linearity, hysteresis, repeatability, and deadband. Af__xrmtr := 0.250% span D - Pressure Transmitter Drift (random and bias) Specified as +/-0.2 % of upper range limit for 30 months (Reference 5.J). Since calibration is performed on a 24 month basis (Assumption 6. 1.1) with a 25% (6 month) grace period, this gives the greatest calibration interval to be 30 months. The upper range limit of the transmitter is specified as 3,000 psig. Per Reference 5.Q, the transmitter/bailey amplifier analyzed drift has been determined to be +/- 11.1 psi or 1.39 % span (random) with a + 2.6 psi or 0.33 % span (bias) applicable over a 30 month calibration interval. This allowance, from the previous channel configuration, is compared in Reference 5.Q Section 7.6.1 to the acceptable limit of +/- 1.20 % span (random) calculated from the applicable uncertainty terms presented in the previous uncertainty calculation which represented the previous channel configuration. Therefore, the uncertainties in the previous calculation for these strings were found to be less than that required to cover the extended calibration interval. The total uncertainty allowances necessary to cover the calibration interval were: RC System Pressure = 11.1 psi/800 psi
- 100 % span = 1.39 % span (random)
RC System Pressure = 2.6 psi/800psi
- 100 % span = 0.33 % span (bias)
To calculate the increased transmitter drift allowance necessary to cover the extended calibration interval uncertainty for the RC System pressure string, a new transmitter drift allowance is determined which will result in a calculated random string uncertainty equal to the random extended calibration allowance determined in Reference 5.Q (+/- 1.39 % span). Therefore, using the Section 7.5 equation of Reference 5.Q. and solving for the necessary drift allowance gives: OSC-8828, Rev 3 Page 14 MEC 07/26/20 10
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 1.392 = 0.252 + x2 + 0.152 + 0.252 + 0.862, Solving for x: x = 1.0223 or approximately 1.02 % span The transmitter drift allowance calculated above will result in a string uncertainty which adequately bounds the random extended calibration interval uncertainty for the RC System Pressure string determined in Reference 5.Q. The + 0.33 % span (bias) term is a new allowance and will be added in its entirety. D pxmtr:= 1.02% span D p_xmtr-bias:= 0.33% span TE - Pressure Transmitter Temperature Effect (random independent) Specified as +/-(0.75% of upper range limit + 0.5% span) per I 00°F change (Reference 5.J). The pressure transmitter's normal temperature environment, including calibration conditions, varies from 60 0F to 120OF (Section 1.4.1). Assuming the transmitters are calibrated at an ambient conditions of 70*F, this results in a maximum temperature change of+/-50'F. Therefore, the temperature effect is TEgxmtr:= 50- F 0.75% 3000 psig +0.5 1.656% span 1.00'~F) *L0 (2500 - 1700) psig O OPE - Pressure Transmitter Overpressure Effect (random independent) Specified as +/-E0.5% upper range limit for a maximum zero shift after 4500 psi overpressure (Reference 5.J). This term is not applicable because the maximum system design RCS pressure is 3250 psia (Reference 5.F.c). Therefore, this effect is neglected. OPE_p._xmtr:= 0% span SPE - Pressure Transmitter Static Pressure Effect (random independent) Specified as -0.5% of input reading per 1000 psig (Reference 5.). However, this term is systematic and is calibrated out before installation. SPE_.p._xmtr:= 0% span PSE - Pressure Transmitter Power Supply Effect (random independent) Per Reference 5.1, specified as less than +/-0.005% of output span per I VDC change (4-20 mA). Per Reference 5.D the power supply for the transmitters is 24 VDC. Maximum DC loop power supply variations are assumed to be within +/-5% of nominal (Assumption 6.1.3). Therefore, the power supply effect is PS~ mr 0.005% - PSE xmtr:=.- x (5%x 24 V) =6.000x 103 %span V LE - Pressure Transmitter Load Effect (random independent) No load effect other than the change in voltage supply to the transmitter is specified (Reference 5.). The pressure transmitters will be calibrated while in the loop and the load during calibration will be the same as during operation (i.e., length of wiring will not change). Therefore, the load effect is LEjpxmtr:= 0% span OSC-8828, Rev 3 Page 15 MEC 07/26/2010
Oconee Nuclear Station Units 1,2, & 3 Digital RI'S RCS Pressure & Temperature I ~Trip Function UncertaintiesI R - Pressure Transmitter Radiation Effect (random independent) The normal radiation effect is negligible. R.p_xmtr := 0% span Combination of Pressure Transmitter Random Independent Error Terms The formula below combines the pressure transmitter random independent error terms. S 2 2 2 2 RU p_xmtr cal:= A_p_xmtr + D_p__xmtr + SPE_p_.xmtr + PSE_p__xmtr ...
+ LE_pjxmtr2 RU p-xmtr.cal = 1.050 % span Rp_xmtr2 RU.pxmtr := 4JRUp_.xmtr_ca? + TE..pxmtr2 + OPE.p_yxmtr2 +
RU..i.xmtr = 1.961% span 7.3.2 Resistance Temperature Detector (RTD) 7.3.2.1 RTD All uncertainties in this section are for a Weed Model N903 I-IA RTD (Reference 5.E). From Reference 5.D, the input and output ranges of the transmitter for each unit are: input: 5200 F to 620OF (assuming the calibrated range remains the same) output: -201 to 221 ohms All uncertainties given below are random-independent terms unless stated otherwise. A - RTD Accuracy (random independent) Specified as = +/-0.3% of calibrated span (Reference 5.K.a). Includes hysteresis and repeatability. A rid := 0.300% span D - RTD Drift (random independent) Specified as +/-0.3°F for 18 month period (Reference 5.K.a). Since calibration is performed on a 24 month basis (Assumption 6. 1.1) with a 25% (6 month) grace period, this gives the greatest calibration interval to be 30 months. Using the SRSS approach, the transmitter drift in percent calibrated span is determined by ratioing the error to the calibrated range of the transmitter. D rtd:= 30 mth 0.3-F
- 18 mth 620 0F - 520OF D rtd=0.387% span OSC-8828, Rev 3 Page 16 MEC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties Combination of RTD Random Independent Error Terms The formula below combines the RTD random independent error terms. RU rtd:= 4Artd2 + Drtd2 RU rtd = 0.490 % span 7.3.2.2 RTD Transmitter All uncertainties in this section are for a Weed Model N7014 series RTD temperature transmitter. From Reference 5.K.b, the input and output ranges of the transmitter for each unit are: input: - 201 to 221 ohms output: 4 to 20 mADC All uncertainties given below are random-independent terms unless stated otherwise. A - RTD Transmitter Accuracy (random independent) Specified as = +/-0.1% of calibrated span (Reference 5.K.b). A rtd xmtr := 0.100% span D - RTD Transmitter Drift (random independent) Specified as having a stability of-O. I % of calibrated span for I year (Reference 5.K.b). Since calibration is performed on a 24 month basis (Assumption 6.1.1) with a 25% (6 month) grace period, this gives the greatest calibration interval to be 30 months. Using the SRSS approach, the transmitter drift in percent calibrated span is determined by ratioing the error to the calibrated range of the transmitter. D rtd xmtr := F x 0.1% 12 mth D rtd xmtr = 0.158% span TE - RTD Transmitter Temperature Effect (random independent) Specified as -+/-(0.3'C+ 0.4% of calibrated span) per 50'C change (Reference 5.K.b). The RTD transmitters normal temperature environment, including calibration conditions, varies from 74 OF to 80'F (Section 1.4.3). Assuming the transmitters are calibrated at ambient conditions of 70'F, this results in a maximum temperature change of+10OF (+/-5.560 C). Therefore, the temperature effect is TErd5.56-C) x 0.3.0C- +0. T xmtr := (, 50°C rid x ,326.67C - 27 + 0.4%1 TErtd xmir =0.105% span OSC-8828, Rev I Page 17 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties RFI - RTD Transmitter Radio-Frequency Interference Effect (random independent) The EMIIRFI term shown in the WEED test report as 3% (Reference 5.K.b). This is a qualification testing value from EPRI TR-107330, section 4.3.7. The 3% should not be used as an uncertainty value for the WEED transmitter. The uncertainty due to the EMIIRFI present in the Teleperm RPS cabinets is assumed to be negligible. RFI rid xmtr:= 0.000% span Combination of RTD Random Independent Error Terms The formula below combines the RTD random independent error terms. 2 2 RU rtd xmtr cal rtd xmrtr + Drid xrmtr + RFI rtdxntr2 _A RU rid xmtr cal= 0.187% span 2 RU ridxmtr RU rid xmr_ca? + TE rid xmtr RU rtd xmtr=0.214% span 7.3.3 Miscellaneous Bias Current Leakage Allowance (+/- Bias) The current leakage effect (associated with cabling and cable penetrations) accounts for instrument uncertainty due to decreased insulation resistance and subsequent current leakage that results from elevated humidity and temperature conditions associated with a high energy line break environment. Since the analysis is during normal conditions, the current leakage allowance for the associated cables between the Reactor Building and the Control Complex are assumed to be negligible.. CL cable:= 0% span Reference Leg Water Compensation (+/- bias) The RCS pressure taps are located on the RCS hot leg at a different elevation from the pressure transmitter. From Reference 5.C the elevation of the pressure transmitters ranges from Elevations 828' and 832'. Each pressure transmitters are corrected for reference leg water compensation so that the pressure represents the pressure at the centerline of the core exit hot leg. This compensation is performed in the calibration procedures in Reference 5.D. Therefore, no additional compensation is needed in this analysis. PMA ref := 0% span RTD Self Heating Effect (+/-bias) Per Reference 5.K.a the error caused by self heating is specified to be 0.01°F with a I mA current through the RTD or 0.02'F with a 2 mA current through the RTD. From Reference 5.D, the current through the RTD is approximately 0.49 mA (100 mV / 204 ohms). The large error is conservatively assumed in this analysis and treated as a + bias. SHErtd := 0.02F 620"F - 520OF SHE rtd = 0.020 % span OSC-8828, Rev 1 Page 18 RGC 07/20/2007
Oconee Ndclear Station Units 1, 2, & 3 [ Digital RPS RCS Pressure & Temperature! Trip Function Uncertainties 7.3.4 TELEPERM TXS Modules All uncertainties in this section are for TELEPERM TXS modules. These modules are located in the Reactor Protection Control Cabinets inside the Control Complex and are not subject to accident induced radiation or pipe rupture environments. All uncertainties given below are random-independent terms and are taken from Reference 5.L unless stated otherwise. 7.3.4.1 XS SAAI Analog Signal Module From References 5.L, the input and output ranges are: input: 4 to 20 mADC output: 0.5 to 2.5 VDC A - SAA I Accuracy (random independent) Specified as = +0% output reading (Reference 5.L). A saal:=0% span D - SAA I Drift (random independent) Specified as +/-0% output reading (Reference 5.L). D saal := 0% span TE - SAA I Temperature Effect (random independent) Specified as -0.31% output reading (Reference 5.L) for a temperature range of 25°C to 75 0 C (77°F to 158°F). The control complex is a controlled environment which specifies temperature to be between 74°F to 80'F (Section 1.4.3). Therefore, the temperature effect is TE saal :- 0.310% x " 2.5 V TE saal=0.388 % span PSE - SAA I Power Supply Effect (random independent) Specified as +/-0% output reading (Reference 5.L). 9 PSE saal := 0% span Combination of SAAI Random Independent Error Terms The formulas below combine the SAA I module random independent error terms. 2 RUsaal_cal:= [A.saal2 + Dsaal + PSEsaal2 RU saal cal = 0.000% span 2 RUsaal := 4RU sal_ca? + TE_saa, RU saal = 0.388% span OSC-8828, Rev 2 Page 19 RGC 02/25/2008
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties
- 7.3.4.2 XS S466 Analog Input Module Reference 5.L specifies the S466 module with a full span of 0 to 2.5 VDC. The output from the SAAI module has a span of 0.5 to 2.5 VDC. This reduced input span incurs a "turn down" effect in the module uncertainty.
A - S466 Accuracy (random independent) Specified as = +/-0.2% of span (Reference 5.L). A s466:= 0.2% span D - S466 Drift (random independent) Specified as +/-0% span (Reference 5.L). D s466:= 0% span TE - S466 Temperature Effect (random independent) Specified as +/-(0.005% span/K x AT) or +/-(0.0028% spanl0 F x AT) where AT = IT - 73.4°F1 (Reference 5.L). The control complex is a controlled environment which specifies temperature to be between 74°F to 800 F (Section 1.4.1). Per Assumption 6.1.5 the temperature within the TXS cabinets is assumed to increase by an additional 20'F. Therefore, the temperature effect is TEs466:= 0.0028% x 180-F + 20°F - 73.4°F1 "F TE-s466 = 0.074 % span PSE - S466 Power Supply Effect (random independent) Specified as +/-0% span (Reference 5.L). PSE s466:= 0% span DSP - S466 Digital Signal Processing Effect (random independent) This is a combination of the single error terms (linearity, repeatability tolerance, and hysteresis). Specified as +0.02%, 0.05%, and 0.05%, span respectively (Reference 5.L). DSPs := 4 + + (0.05%) DSP s466 = 0.073 % span Combination of S466 Random Independent Error Terms The formulas below combine the S466 module random independent error terms. RUs466_cal:= 4As4662 + Ds4662 + PSE s4662 + DSP s4662 x (2.5 V -0 V) RUJs466_cal= 0.266% span s466x 2.5 V- V 2 RU s466:= ca?+ TE _RUs466 RUs4 %V-s6 0 0.5 V. R U s466 = 0.282 % span OSC-8828, Rev 2 Page 20 RGC 02/25/2008
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 7.3.5 Calibration Effect 7.3.5.1 RCS Pressure Measurement & Test Equipment (random independent) Calibration procedures state the types of measurement and test equipment to be used when calibrating the instrument loops. From Reference 5.D.a the following equipment is required for the calibration of TXS modules: 0 Current Source, Altek 434 Reference 5.1 specifies the current source to be +/-0.0304 mA for equipment used inside the Control Complex. 0.0304 mA MTEcurrent_p_rack:= (20 - 4) mA MTEcurrent._prack= 0.190 % span The output through the TXS modules are recorded off the OAC. Since the OAC is receiving digitized readings from the TXS digital processors via the Maintenance Service Interface (MSI) computer through the TXS Gateway computer, only the resolution of the OAC reading is applied. From Reference 5.D.a (Enclosures 11.2.5 and 11.3.5) the resolution from the digital OAC point is one decimal point. 0.1 psig MTEoacprack:= (2500.0 - 1700.0) psig MTEoac_p_rack =0.013 % span From Reference 5.D.b the following equipment is required for the pressure transmitter:
- Digital multimeter, Agilent 34401A
- Pressure tester, Mensor DPGII 15000 (0-2500 psig) or Heise PTE-l with HQS-2 (0-2500 psig)
Reference 5.1 specifies the digital multimeter uncertainty to be +/-0.03644 mA. The pressure transmitters are calibrated using the 4 to 20 mADC range. 0.03644 mA MTEdmm_p_xmtr:= (20 - 4) mA MTEdmm_p__xmtr = 0.228 % span The pressure tester that is used during transmitter calibration is the Mensor DPGII 15000 or the Heise HQS-2. Reference 5.1 specifies the pressure tester to be +/-1.4151 psi or +6.6313 psi, respectively. The bounding value is used in this analysis. 6.6313 psi MTE_pressy.xmIr:= (2500 - 1700) psi MTE_press__p_xmtr = 0.829 % span OSC-8828, Rev 2 Page 21 RGC 02125/2008
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties The following combines the M&TE random independent error terms. MTE_pressrack:= ,MTEcurrent.p_ rack2 + MTEoac_pfrack2 MTEjpress rack = 0.190% span MTE_pressxmtr:= ,MTEdmm_pxmtr2 + MTEpress..pxmtr2 MTEpress_xmtr = 0.860% span Calibration/Setting Tolerance Term Identification (random independent) Since the calibration of these strings does not verify all the attributes of each component's reference accuracy (repeatability, linearity, and hysteresis), a calibration tolerance will be included in addition to each reference accuracy. The calibration tolerance is the acceptable 'as-left' setting band when the calibration is done on a component by component basis. The SAAI and S466 modules cannot be calibrated; however, the loop can be checked to verify the TXS component loop uncertainty is within the specified acceptance criteria. If the modules are outside the acceptance criteria, the modules are replaced and the loop is re-checked. The loop is checked by applying 4-20 mADC at the SAA1 and reading the pressure values at the OAC. Therefore, the as-found/as-left calibration acceptance criteria are identical to the reference accuracies of the TXS modules. Per Assumption 6.1.6, the reference accuracy of SAAM is assumed to be 0.05% span. RA saal := 0.05% span RAs466:= A_s466 x 2.5 V V D-_0
ý2.5 V -0.5V)
RA s466 = 0.250 % span 2 2 CTE__press__rack := 4RAsaal + RAJs466 CTEpress_rack = 0.255 % span Calibration tolerances for the transmitters are taken from Reference 5.D.b. The 'as-left' tolerance is
+/-0.25% span (+/-0.04 mADC).
CTEpressxmtr:= 0.25% span Calibration Effect The overall calibration effect (CE) for the RCS pressure loop is as follows. 2 2 CE_press:= MTEpress-xmtr + CTE.press xmtr ... 2
+ MTE_pressrack2 + CTE__pressrack CE_press = 0.950% span 9
OSC-8828, Rev 2 Page 22 RGC 02/25/2008
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 7.3.5.2 RCS Temperature Measurement & Test Equipment (random independent) Calibration procedures state the types of measurement and test equipment to be used when calibrating the instrument loops. From Reference 5.D.a the following equipment is required for the calibration of TXS modules: 0 Current Source, Altek 434 Reference 5.1 specifies the current source to be +/-0.0304 mA for equipment used inside the Control Complex. MTE current track := MTEcurrent_p_rack MTE current t rack = 0.190 % span The output through the TXS modules are recorded off the OAC. From Reference 5.D.a (Enclosure 11.2.6 and 11.3.6) the resolution from the digital OAC point is two decimal points. 0.01 OF MTE oac t rack= (620.00 - 520.00) OF MTE oac t rack=0.010% span From Reference 5.D.c the following equipment is required for the temperature transmitter:
- Digital multimeter, Agilent 34401A 0 RTD Resistance Simulator, General Resistance Model RDS 52A Reference 5.1 specifies the digital multimeter uncertainty to be +/-0.03644 mA. The pressure transmitters are calibrated using the 4 to 20 mADC range.
MTE_dmmt:= 0.03644 mA (20 - 4) mA MTE dmmrt = 0.228 % span Reference 5.1 (Attachment 18) specifies the RTD resistance simulator for inside the Control Complex as follows: Resis setting:= 221 ) MTE_resis := 1(0.0001 x Resissetting + 0.0015 f))2+ (0.000, x Resissetting + 0.0015 Q)2 J+ (0.000015 x Resissetting x 15.33)2 + (0.01 2)2 MTE resis = 0.062fl MTE_resis t xmtr . MTE resis (221 - 201) n MTE resis t xmtr = 0.308 % span 0_ OSC-8828, Rev I Page23 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties The RTD cannot be calibrated; however, they can be checked to verify if it is within the specified acceptance criteria. If the RTDs are outside the acceptance criteria, the RTD is replaced and re-checked. The RTD is checked only with a digital multimeter. Therefore, the measurement equipment for the RTD check is assumed to be the Agilent 34401 A. Reference 5.1 specifies the digital multimeter uncertainty to be +/-0.25128 ohm. The RTDs are calibrated between 201 to 221 ohm range. MTE- drmmrtd:= 0.25128 f)
-d (221 - 201) Q MTE dmm rtd= 1.256% span The following combines the M&TE random independent error terms.
MTEtemp txs = MTE current t rack2 + MTE oac t rack2 MTE temptxs =0.190 % span 12 2 MTE temp ,xmtr: MTEresistxmtr + MTEdmm_t MTE-temp_xmtr = 0.383 % span MTEtemp rack:= ,MTE temptxs2 + MTE_temp_.xmtr2 MTEtemp_rack = 0.428 % span MTEtemp_rtd:= MTE_dmm_rtd MTE temp_rtd = 1.256 % span Calibration/Setting Tolerance Term Identification (random independent) Since the calibration of the RTDs and RTD transmitters does not verify all the attributes of each component's reference accuracy (repeatability, linearity, and hysteresis), a calibration tolerance will be included in addition to each reference accuracy. The calibration tolerance is the acceptable 'as-left' setting band when the calibration is done on a component by component basis. The SAA1 and S466 modules cannot be calibrated; however, the loop can be checked to verify the TXS component loop uncertainty is within the specified acceptance criteria. If the modules are outside the acceptance criteria, the modules are replaced and the loop is re-checked. The loop is checked by applying 4-20 mADC at the SAAI and reading the temperature values at the OAC. Therefore, the as-found/as-left calibration acceptance criteria are identical to the reference accuracies of the TXS modules. Per Assumption 6.1.6, the reference accuracy of SAAI is assumed to be 0.05% span. RA saal = 0.050% span RA s466 = 0.250 % span 2 CTE temp_rack := 4RAsaal + RAs4662 CTE-temp-rack = 0.255 % span 0 OSC-8828, Rev I Page 24 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties The as-found/as-left calibration acceptance criteria for the RTDs are assumed to be identical to the reference accuracy. If the RTDs are outside the acceptance criteria, the modules are replaced and the RTD is re-checked. CTE temp_rd:= A_rtd CTE temp_rid =0.300% span The as-found/as-left calibration acceptance criteria for the RTD transmitters are assumed to be identical to the reference accuracy. CTEtempxmtr := A rtd xmtr CTE temp__xmtr = 0. 100 % span Calibration Effect The overall calibration effect (CE) for the RCS temperature loop is as follows. E temp:= MTE_temp_txs + CTEtemprack + MTE_tempxmtr ...
+ CTEtemp xmtr2 + MTE_temprtd2 + CTE_temp rtd2 CEtemp = 1.388 % span OSC-8828, Rev I Page 25 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 7.4 Initial Condition Uncertainty Determination The initial condition uncertainty (ICU) will be determined utilizing Eq. 3-1 with the device uncertainties calculated in Section 7.3. 7.4.1 High and Low RCS Pressure Uncertainties The high and low RCS pressure initial conditions involve module strings with similar components. This loop consists of the pressure transmitter, SAA I, and S466. Therefore, a single total uncertainty can be calculated for conditions and functions for which the loop is required. 2 2 2
+ CE..ress ICU_press_random:=4RU p__xmtr2 + RU saal + RUs466 ICU.pressbias:=CLcable + PMA ref + D_p_xmrtr._bias ICU press:= ICU_pressrandom+ ICU pressbias ICUpress= 2.561 % span IC_press:= ICUpress x (2500 psig - 1700 psig)
IC_.press = 20.490 psi 7.4.2 High RCS Temperature Uncertainties The high RCS temperature initial conditions involve module strings with similar components. This loop consists of the RTD, RTD transmitter, SAAI, and S466. Therefore, a single total uncertainty can be calculated for conditions and functions for which the loop is required. ICU temprandom:= 4RU rtd2 + RU rid xmt2 + RUsaal2 + RU s4662 + CE temp2 ICU-temp_bias:= CLcable + SHE_rtd ICU-temp:= ICUtemp_random+ ICU tempbias ICU-temp = 1.583 % span IC-tenp:= ICU-temp x (620 0 F - 520 'F) IC temp = 1.583 *F OSC-8828. Rev 3 Page 26 MEC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 7.4.3 Variable Low RCS Pressure Uncertainties The variable low RCS pressure initial conditions is a combination of the RCS pressure loop and the RCS temperature loop. Therefore, a single total uncertainty can be calculated for conditions and functions for which the loop is required. ICUvariablerandom:= ICU'_pressrandom2 ... 2
+ [ICU~temp random x 620-F- 520-F (11.14 psi ~
2500 psig - 1700 psigj x -F ICU-variablebias:=ICU_pressbias ...
+b 2500 psig - 1700 psig) -F A ICUvariable:=ICU variable random + ICU variable-bias ICU variable = 3.475 % span IC variable:=ICU variable x (2500 psig - 1700 psig)
IC_variable= 27.797 psi 7.5 Total Loop Uncertainty Determination The total loop uncertainty (TLU) will be determined utilizing Eq. 3-1 and the device uncertainties calculated in Section 7.3. 7.5.1 High and Low RCS Pressure Uncertainties The high and low RCS pressure trip uncertainties involve module strings with similar components. This loop consists of the pressure transmitter, SAAI, and S466. Therefore, a single total uncertainty can be calculated for conditions and functions for which the loop is required. TL U_press:= ICUpress_random+ ICUjpressbias TLU-press = 2.561% span TLUpresstvosided:= TLUjpress x (2500 psig - 1700 psig) TLUgpress two sided = 20.490 psi TLU press-sigma:= ICUgpress-randomx a-_reduction + ICU press bias TLUgpress-one-sided:= TLU presssigma x (2500 psig - 1700 psig) TLU press one sided = 17.634 psi OSC-8828, Rev 3 Page 27 MEC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 7.5.2 High RCS Temperature Uncertainties The high RCS temperature trip uncertainty involve module strings with similar components. This loop consists of the RTD, RTD transmitter, SAA1, and S466. Therefore, a single total uncertainty can be calculated for conditions and functions for which the loop is required. TLU temp:= ICUtemprandom+ ICU tempbias TLU temp = 1.583% span TLU-temp_twosided:= TLU temp x (620*F - 520 'F) TLU temptwosided= 1.583'F TLU temp__sigma := ICU temprandom x oreduction+ ICU tempbias TLU temp_onesided:= TLU.temp__sigma x (620*F - 520 'F) TLU temponesided = 1.333'F 7.5.3 Variable RCS Low Pressure Uncertainties The variable low RCS pressure trip uncertainty is a combination of the RCS pressure loop and the RCS temperature loop. Therefore, a single total uncertainty can be calculated for conditions and functions for which the loop is required. TLU variable := ICU variable random + ICU-variable-bias TLUvariable = 3.475 % span TLUvariabletwosided:=TLUvariable x (2500 psig - 1700 psig) TL U_variable_twosided= 27.797 psi TLU-variable.sigma:=ICU variablerandomx crreduction+ ICUvariablebias TLU-variableonesided:=TLUvariable-sigma x (2500 psig - 1700 psig) TLU_variableonesided= 23.807 psi 7.6 Rack Uncertainty This is the uncertainty associated with the indicated parameter up to the plant setpoint. This term will be identified as "etrip". Basically, this involves the statistical combination (SRSS) ofall uncertainty (error) terms associated with the rack components. 7.6.1 High RCS Pressure RU high_press:= RU saal ca? + RU s466 ca? ... 2 2 rack
+ MTEpressrack + CTEpress RUhigh-press = 0.415 % span etriphighpress = RU highpressx (2500 psig - 1700 psig) etriphigh_press = 3.32 psi OSC-8828, Rev 3 Page 28 MEC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties As requested by ONS personnel, the following calculates the uncertainty starting at the pressure transmitter through the rack components to the OAC display for the calibration string. Therefore, only the M&TE used are the pressure tester and the read out from the OAC. RUhigh_press-string:= RU saalca? + RU s466 cal + RU._i xmtr ca? ... 1.410% span 2 - 2
+ MTEjpress..p_.xmtr + MTEoac..prack ...
2 2 I+ CTE press xmtr + CTE_press_rack Dp__xmtr.bias = 0.330% span high.press_string:=RU high.pressstring+ D_p xmtr bias = 1.740% span etrip-high_press._string= highpress string x (2500 psig - 1700 psig) etrip-high_press__string 13.921 psi 7.6.2 Low RCS Pressure J RU_low_press:= RU saalca?+ RU s466_ca? ...
-c?_
J+ MTE._press_rack 2-C~~esrc 2 RU-low.press = 0.415 % span etripjowpress = RU low_press x (2500 psig - 1700 psig) a etrip-lowpress= 3.320 psi As requested by ONS personnel, the following calculates the uncertainty starting at the pressure transmitter through the rack components to the OAC display for the calibration string. Therefore, only the M&TE used are the pressure tester and the read out from the OAC. RUIowpress...string:= RU saal cal? + RU 2s466_ca? + RU_pxrmtr 2z ca? ... 1.410% span
+ MTE_press_pxmtr + MTE oac~p rack ...
+ CTE_press xmtr + CTE rack2ress D._p_xmtr_bias = 0.330 % span low_press string := RUlowpressstring+ DQp__xmtr bias = 1.740 % span etripoiow_press string lowpress string x (2500 psig - 1700 psig) etrip lowvpress string = 13.921 psi 7.6.3 High RCS Temperature RUhighktemp := RU rtd xmtr ca? + RU saal ca? + RU s466_ca? ...
+ MTE temprack + CTEtemp rack + CTEtempxmtr RUhightemp = 0.603 % span etrip-highktemp = RU hightemp x (620'F - 520'F) etrip-highjtemp = 0.603 'F OSC-8828, Rev 3 Page 29 MEC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties 7.6.4 Variable Low RCS Pressure 2 RU-variabepres:= _lowpress ... j+[R hi~ tep (2500 psig - 1700 psig) X OF) RUvariable._press= 0.937% span etripvariable.press= RUvariablepressx (2500 psig - 1700 psig) etripvariablepress= 7.496psi As requested by ONS personnel, the following calculates the uncertainty starting at the pressure transmitter through the rack components to the OAC display for the calibration string. Therefore, only the M&TE used are the pressure tester and the read out from the OAC. RUvariable string:= RUlow.ipressstring .... 1.641% span RU+ high Rý_ih tempx (tm 620OF - 520OF J psi'l (11.14Fpsi
-Jk2500 psig 1700 psig)
D_p_xmtrbias=0.330% span variable_string:=RUvariablestring+ D_p_xmtrbias = 1.971 % span etripvariable string = variable_stringx (2500 psig - 1700 psig) etripvariable string = 15.771 psi 7.7 Core Exit to Hot Leg Tap Pressure Drop The variable low RCS pressure safety limits define the hot leg temperature as function of core exit pressure at which the predicted DNBR would equal the design limit. The variable low RCS pressure trip function measures RCS pressure in the hot legs. Therefore, an allowance to account for pressure drop between the core exit and hot leg tap must be determined. This pressure drop will vary depending on the number of reactor coolant pumps operating. The Oconee Technical Specifications only allow operation with 3 or 4 reactor coolant pumps while at power. The core exit to hot leg tap pressure drops for these pump combinations are as follows (Reference 5.N): RCP Combination RCS Flow (gpm) AP (psi) 2/2 352000 49 2/1 263435 53 i/2 263435 19 A lower pressure drop adjustment will result in a higher setpoint. The pressure drop between the core exit and hot leg is a function of the static head and the square of the flow rate. Reference 5.N states that these pressure drops are based on an analysis of Midland. Reference 5.N also states that the only difference in the pressure drop calculation for Oconee versus Midland is the assumed flow rate. For example, the Oconee pressure drop calculations are based on an RCS flow of 374880 gpm (106.5% design flow) versus 352000 gpm (100% design flow) for Midland. The pressure drop increases from 49 psi to about 55.6 psi (= 1.0652 x 49). This agrees well with the RETRAN model predictions (Reference 5.M). Therefore, the values in the above table are conservatively low estimates of the actual core exit to hot leg tap pressure drop. Pdrop_4rcp:=49 psi Pdrop_3rcp:= 19 psi OSC-8828, Rev 3 Page 30 MEC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties O 7.8 Variable Low RCS Pressure Safety Limit For a given hot leg temperature, the variable low RCS pressure COLR setpoint defines the minimum possible hot leg pressure at which the reactor can trip. The variable low RCS pressure safety limit is determined by adjusting the COLR specified setpoint by an allowance to account for instrument uncertainty. From the previous section, an instrument uncertainty allowance of 30 psi is assumed. The following equation defines the safety limit at the hot leg tap in psig. Utilizing the Statistical Core Design (SCD) methodology, another variable low RCS pressure safety limit is calculated without the instrument uncertainty. ThU variable-max:= 30 psi SL-hotleg:= 11.14 x Thot - 4706 - TLUvariablemax SL-hotleg:= 11.14 x Thot - 4736 SL-hotleg_SCD: 11.14 x Thot - 4706 This safety limit can be converted to a core exit pressure limit by accounting for the core exit to hot leg tap pressure drop. Since this pressure drop varies as a function of RCS flow, different safety limits for three and four reactor coolant pump operation are determined. SLcoreexit_4rcp:= 11.14 x Thot - 4706 - TLUvariablemrax+ P_drop_4rcp+ 14.7 SLcoreexit.4rcp := 11.14 x Thot - 4672.3 SL coreexit.4rcpSCD:= 11.14 x Thot - 4706 + Pdrop_4rcp+ 14.7 SL-coree-xit_4rcp__SCD:= 11.14 x Thot - 4642.3 SL_coreexit_3rcp 11.14 x T hot - 4706 - TLU variable_max + P_drop_3rcp + 14.7 SLcoreexit_3rcp 11.14 x Thot - 4702.3 SLcoreexit3rcpSCD 11.14 x T__hot - 4706 + P drop_3rcp + 14.7 SLcoreexit_3rcpSCD 11.14 x Thot - 4672.3 These core exit variable low RCS pressure safety limits are tabulated below. This data is used to generate the core protection safety limits shown in Figure 7-2. 0 OSC-8828, Rev I Page 31 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RIPS RCS Pressure & Temperature Trip Function Uncertainties 0 Non-SCD Variable Low RCS Pressure Safety Limit Core Exit Pressure (psia) 4 RCP T-hot ('F) 3 RCP T hot (OF) 1800 581.0 583.7 1900 590.0 592.7 2000 598.9 601.6 2100 607.9 610.6 2200 616.9 619.6 2300 625.9 628.6 SCD Variable Low RCS Pressure Safety Limit Core Exit Pressure (psia) 4 RCP T-hot ('F) 3 RCP T hot (OF) 1800 578.3 581.0 1900 587.3 590.0 2000 596.3 598.9 2100 605.2 607.9 2200 614.2 616.9 2300 623.2 625.9 OCONEE NUCLEAR STATION UNITS 1, 2, AND 3 CORE PROTECTION SAFETY LIMITS 2100
~2000
_ 1900 1800 570 580 590 600 610 620 630 640 REACTOR COOLANT OUTLET TEMPERATURE Figure 7-2 OSC-8828, Rev 1 Page 32 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 . [ Digital RPS RCS Pressure & Temperature Trip Function Uncertainties The statepoints for the RPS MAPs are defined as the intersections of the variable low pressure safety limits with the low RCS pressure and high RCS temperature safety limits. The low RCS pressure and the high RCS temperature Technical Specification setpoints are 1800 psia and 618'F (Reference 4.2, Table 3.3.1-1), respectively. An instrument uncertainty allowance of 30 psi and 2°F are assumed for the low RCS pressure and the high RCS temperature trip functions, respectively. TLU_.press_max:= 30 psi TLU-temp_max:= 2*F SLlow_press_4rcp 1800 psig - TLU pressmax + P_drop_4rcp + 14.7 psi 0 SLlow_press_4rcp = 1833.7 psia SLIowpress_4rcpSCD:= 1800 psig + Pdrop_4rcp+ 14.7 psi SLlowpress4rcp_.SCD = 1863.7 psia SL lowypress._3rcp 1800 psig - TiU_pressmax + P_dropj3rcp + 14.7 psi SLlow_press_3rcp 1803.7 psia SLIowpress_3rcpSCD:= 1800 psig + P drop_3rcp + 14.7 psi SLIow_press_3rcpSCD = 1833.7 psia SLhighjtemp 618'F + TLU_temp max SLhigh.temp = 620.000 -F SL_hightempSCD := 618°F A pressure of 1800 psia (1830 psia for SCD) at the core exit is selected as a conservative low RCS pressure safety limit This value bounds both the 4 reactor coolant pump and the 3 reactor coolant pump safety limits calculated above. The RPS MAP statepoints are determined by interpolating on the variable low RCS pressure safety limits with a low RCS pressure of 1800 psia (1830 psia for SCD) and a high temperature of 620*F (618'F for SCD). Non-S CD Variable Low RCS Pressure Safety Limit 4 RCP MAP Statepoint Core Exit Pressure (psia) Hot Leg Temperature (OF) High Temperature 2235 620.0 Low Pressure 1800 581.0 3 RCP MAP Statepoint Core Exit Pressure (psia) Hot Leg Temperature, (F) High Temperature 2205 620.0 Low Pressure 1800 583.7 SCD Variable Low RCS Pressure Safety Limit 4 RCP MAP Statepoint Core Exit Pressure (psia) Hot Leg Temperature ('F) High Temperature 2242 618.0 Low Pressure 1830 581.0 3 RCP MAP Statepoint Core Exit Pressure (psia) Hot Leg Temperature ('F) 0 High Temperature Low Pressure 2212 1830 618.0 583.7 OSC-8828, Rev I Page 33 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties O 7.9 Setpoint Analysis An evaluation of the RPS setpoint with respect to the instrument loop uncertainty is presented here. The analytical (or safety analysis) limit is the measured of calculated variable established by the UFSAR Chapter 15 safety analyses to ensure that the safety limit is not exceeded. The safety limit is a limit on a process variable that is necessary to reasonably protect the integrity of the physical barriers that guard against the uncontrolled release of radioactivity. The difference between the analytical limit and the Technical Specification setpoint (or RPS setpoint), is the total allowance, and should at a minimum account for instrument uncertainty. Normally, the plant will adjust the Technical Specification by a certain amount. This adjustment assures that adequate margin is included to avoid Technical Specification violations. 7.9.1 High RCS Pressure Trip Function From Technical Specification 33.1 Table 3.3.1-1, the high RCS pressure trip setpoint is 2355 psig. From Reference 5.M, the plant setpoint is 2345 psig. SPhigh..press 2355 psig PS~highpress 2345 psig The RCS high pressure trip function along with the pressurizer safety valve (actuation setpoint 2500 psig Technical Specification Bases 3.4.10) have been established to assure never reaching the RCS pressure safety limit (2735 psig Technical Specification Bases 3.3.1). The most limiting peak primary pressure accident is the Startup Event from HZP (Reference 5.P). This analysis assumed an initial condition uncertainty of 30 psi and a high RCS pressure trip function of 7 psi for a total of 37 psi. Based on the fact that the RCS high pressure trip TLU and the analyzed peak pressure is less than 2750 psia, it can be concluded that a conservative high RCS trip setpoint is selected. 7.9.2 RCS Low Pressure Trip Function From Technical Specification 3.3.1 Table 3.3.1-1, the RCS low pressure trip setpoint is 1800 psig (hot leg tap). From Reference 5.M, the plant setpoint is 1810 psig (hot leg tap). The analytical limit is 1800 psia (core exit), which is constrained by the variable low RCS pressure safety limit. SP low press:= 1800 psig PS low Press 1810 psig ALlowpress 1800 psia - Pdrop_3rcp - 14.7 psi ALlowpress = 1766.3 psig TA-lowpress := SPlowpress - ALlowpress TAlowpress = 33.700 psig The total allowance to the Technical Specification low RCS pressure setpoint is greater than the total instrument loop uncertainty calculated in Section 7.5.1. Therefore, a conservative low RCS pressure setpoint is selected. 0 OSC-8828, Rev I Page 34 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties D7.9.3 RCS High Temperature Trip Function From Technical Specification 3.3.1 Table 3.3.1-1, the RCS high temperature trip setpoint is 6181F. From Reference 5.M, the plant setpoint is 6171F. Per Reference 5.M, the analytical limit is 620*F, which is the maximum allowable RCS temperature due to licensing basis analyses or other constraint such as the variable low RCS pressure safety limit. SPhightemp:=61 8°F PS hightemp := 617 *F ALhigh temp := 620*F TA hightemp:= ALhigkhtemp - SP highjtemp TA.highktemp = 2.000°F The total allowance to the Technical Specification high RCS temperature setpoint is greater than the total instrument loop uncertainty calculated in Section 7.5.2. Therefore, a conservative high RCS temperature setpoint is selected. 7.9.4 Variable Low RCS Pressure Trip Function The allowance to the Technical Specification variable low RCS pressure setpoint is 30 psi, which is greater than the total instrument loop uncertainty calculated in Section 7.5.3. Therefore, a conservative variable low RCS pressure setpoint is selected. D7.10 Loop Scaling The scaling on the RCS pressure transmitter is 4 to 20 mA which corresponds to the range of 1700 to 2500 psig for Modes I and 2 (Reference 5.D.c). DEuring LTOP ep.ratien., !he RS* pressure transmiter scaling is 4 to 20 mA which czrrczpends te the range efO to! 600 psig (Refecrcncc 5.D).E)-. The scaling on the RCS temperature transmitter is 201 to 221 ohms which corresponds to the range of 5207F to 6207F (Reference 5.D.b). OSC-8828, Rev 3 Page 35 M EC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature I Trip Function Uncertainties 7.11 As-Found Tolerance Determination The purpose of this section is to determine how much uncertainty, which may appear during the "as-found" portion of the loop calibration, has been accounted for in the total loop uncertainties calculated in Section 7.5. Values recorded during loop as-found calibration which are less than those documented in this section would require no additional documentation. However, values recorded during loop as-found calibration which exceed those documented in this section would require a more detailed review to determine the effects of the increased uncertainty. The following uncertainty terms are applicable when determining the loop past operability values, reference accuracy (A), drift (D), setting tolerance (CTE), measurement and test equipment (MTE) and resolution (RES). All data and equations used in this section were taken from previous sections of this calculation. 7.11.1 RCS Pressure The RCS pressure instrument string consists of the transmitter, SAAI, 5466, and OAC, therefore, the uncertainty terms are as follows: RA_press.xmtr := A_pxmtr D_press_xmtr := Dp._xmtr = 1.020 % span RApressxmtr = 0.250% span D__._xmtrbias = 0.330% span CTE.pressxmtr = 0.250% span MTEpressxmtr = 0.860% span RA saal = 0.050% span D saal = 0.000% span RA s466 = 0.250 % span D s466 = 0.000% span CTrEpress rack = 0.255 % span MTE-press rack = 0.190 % span The as-found tolerance is calculated as follows: AT_pressxmtr := RApress S2 xmtr + D_press xmtr2 ... + D pxmtrbias
- 2 -2
+ CTEjpressxmtr + MTE~press_xmrtr A Tpress.xmtr = 1.710% span A T_p_xmtr := ATjpress xmtr x (20 - 4) mA AT.p_xmtr = 0.274mA AT.press rack := RA saal2 + RAs4662 + D_ saal 2 + D s4662
+ CTE_press rack2 + MTE_pressrack ATfpress rack = 0.408% span ATjprack := AT__pressrack x (2500 - 1700) psig ATprack = 3.262 psi OSC-8828, Rev 3 Page 36 M EC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uncertainties O 7.11.2 RCS Temperature The RCS temperature instrument string consists of the RTD, transmitter, SAAI, S466, and OAC, therefore, the uncertainty terms are as follows: RA temp_rtd := A_rid Ditemprtd:=D_rid RA temp rid = 0.300 % span D-temp-rd= 0.387 % span CTE temp_rtd= 0.300% span MTE temp rtd = 1.256% span RAtempxmtr := A-rtd xmtr D-tempxmtr := D rtd xmtr RAtempxmtr =0.100% span D-tempxmtr =0.158% span CTE temp_xmtr = 0.100% span MTE temp xmtr =0.383% span RA saal = 0.050% span D saal = 0.000% span RAs466=0.250% span Ds466 = 0.000 % span CTE temp*_rack = 0.255 % span MTE temp xxs =0.190 % span The as-found tolerance is calculated as follows: AT temprId := JRA-temprtd2+ Demp_!d2.. 2
, + CTýtemp-rtd2 + MTE_Iemprtid AT temp rtd = 1.381 % span AT t_rtd:= AT temprtdx (221 - 201) Q AT t1rtd = 0.276 0 AT temp xmIr := RA-temp._xmtr2 + D-tempxmtr2 ...
I+CT~_em xmtr ++ MTE_temp
+ CTE_temp MT xmtr ATTtemp__xmtr-= 0.438% span AT t xmtr:= ATtempxmtr x (20- 4) mA AT t xmtr = 0.070mA AT temprack := IRA saal2 + RAJs4662 + D saai2 + D-s4662 J+ CTE temp rack2+ MTEtemp txs2 A T temp rack =0.408% span AT t rack := AT_temp rack x (620 - 520) 'F ATtrack = 0.408'F QSC-8828, Rev I Page 37 RGC 07/20/2007
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature I Trip Function Uncertainties D 8. Maintenance Calibration Requirements Maintenance calibration requirements should be performed consistent with Reference 5.D:
- 9. Reactivity Management This calculation involves the determination of the RPS RCS pressure and temperature trip functions uncertainties and the variable low RCS pressure safety limit. The determination of the overall uncertainties and variable low RCS pressure safety limit has no bearing on reactivity management issues.
The application of the uncertainty, however, may affect reactivity management - which should be addressed in those applications. Therefore, with respect to this analysis there is no reactivity management concerns.
- 10. Conclusions This calculation determines the total loop uncertainty in accordance with EDM-I 02 guidance for the variable low RCS pressure, low RCS pressure, high RCS pressure, and high RCS temperature trip functions in support of the Oconee Digital Reactor Protection System Replacement Project. Each of these uncertainties are summarized below. In addition, this calculation determines the safety limit for the variable low RCS pressure trip function.
"Description" "TLU" "Unit" ý p "RCS High Pressure Initial Condition (W)"
"RCS Low Pressure Initial Condition (Y)"
"RCS High Temperature Initial Condition (+/-)"
20.49 20.49 1.58 "psi" "psi"
OF
"RCS Variable Low Pressure Initial Condition (+)" 27.8 "psi" "RCS High Pressure Trip Uncertainty (+/- two-sided)" 20.49 "psi" TLU total = "RCS High Pressure Trip Uncertainty (= one-sided)" 17.63 "psi" "RCS Low Pressure Trip Uncertainty (+ two-sided)" 20.49 "psi"
.Psi" "RCS Low Pressure Trip Uncertainty (+ one-sided)" 17.63 I.
"OF" "RCS High Temperature Trip Uncertainty (+/- two-sided)" 1.58 "RCS High Temperature Trip Uncertainty (+ one-sided)" 1.33 "OF" "psi" "RCS Variable Low Pressure Trip Uncertainty (= two-sided)" 27.8 "psi,,
"RCS Variable Low Pressure Trip Uncertainty (o one-sided)" 23.81 OSC-8828, Rev 3 Page 38 MEC 07/26/2010
Oconee Nuclear Station Units 1, 2, & 3 Digital RPS RCS Pressure & Temperature Trip Function Uincertainties p The following summarizes the maximum in-plant trip setpoint adjustment which is the difference between the nominal trip setpoint and the indicated parameter value at the point when trip actuation Occurs.
"Description" "Trip Uncertainty" "Unit" "RCS High Pressure Trip Rack (=)" 3.32 "psi" "RCS High Pressure Trip String (=)" 13.92 "psi-
"RCS Low Pressure Trip Rack (-)" 3.32 "psi" etrip = "psi" "RCS Low Pressure Trip String (=)" 13.92
",OF,"
"RCS High Temperature Trip Rack (i)" 0.6 "RCS Variable Low Pressure Trip Rack (+)" 7.5 "psit" "RCS Variable Low Pressure Trip String (+)" 15.77 "psi" I
The following summarizes the allowable as-found tolerance for each component "Description" "Allowable Tollerance" "Unit" "RCS Pressure Transmitter (*)" 0.27 "mA" "RCS Pressure Rack (+/-)" 3.3 "psi"" AT =
"RCS Temperature RTD (+/-)" 0.28 "ohms" "RCS Temperature Transmitter (t)" 0.07 "mA"
,,OF",
"RCS Temperature Rack (+/-)" 0.41 0
OSC-8828. Rev 3 Page 39 MEC 07/26/2010
APPENDIX A REDSAR MARKUP SECTION II - MANEUVERING ANALYSIS OSC-8828 Rev. 1 Page 40 RGC 07/2012007 Appendix A
S I. COLR REFERENCES The analytical methods used to determine core operating limits for parameters identified in Technical Specifications and provided in the COLR shall be those previously reviewed and approved by the NRC as specified in Technical Specification 5.6.5b. The complete identification of the topical reports referenced in the COLR (i.e., report number, title, revision number, report date or NRC SER date, and any supplements) are described in the following documents. BAW-10192-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam GeneratorPlants, Rev. 0, (SER dated Feb. 18, 1997.) Includes updated referenced topical reports:
- 1) BAW-10164P-A, Rev. 4, "RELAP/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis", SER dated April 9,2002. 2) BAW-10166-P-A, "BEACH - Best Estimate Analysis Core Heat Transfer, A Computer Program For Reflood Heat Transfer During LOCA" (TAC No. MC0341), SER dated November 7, 2003.
- 1. DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 3, SER dated 9/24/03.
- 2. DPC-NE-3005-PA, UFSAR Chapter 15 Transient Analysis Methodology, Rev. 2, SER dated 9/24/03.
- 3. BAW-10227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, Rev. 1, June 2003 (SER to BAW-10186P-Adated June 18, 2003).
. REFERENCES
- 1. OSC-6922, Main Steam Line Break Dose Analysis, Revision 7.
- 2. OSC-6221, "FSAR Section 15.2 - Startup Accident", Rev. 5, 2/10/05.
OSC-8128, "ROTSG UFSAR Section 15.17 - Small Steam Line Break DNBR Analysis", Rev. 6, dated 1/31/05.
- 3. OSC-7981, "ROTSG UFSAR Section 15.6 Loss of Flow", Rev. 0, dated 03/12/02.
OSC-7982, "ROTSG UFSAR Section 15.6 - Loss of Flow DNBR", Rev. 1, dated 09/30/04.
- 4. AREVA Document 51-5056748-00, "ONS-2 CY22 LOCA Checks Document", dated 01/19/05.
- 5. 08C= 4048, "RPS RCS Pfessure and Temper-ature Trip Functien Uncertainty Analyses, and Var-ial Lew Pressure Safety Limit", Rev. 4, dated 1131/0 1.
OSC-8828, "Digital RPS RCS Pressure & Temperature Trip Function Uncertainties and Variable Low RCS Pressure Safety Limit", Rev. / 3
- 6. OSC-3416, "RPS Flux/Flow Ratio Uncertainty Evaluation", Rev. 3, dated 11/17/95.
- 7. OSC-7334, "Determination of Limiting DNB Transient", Rev. 2, dated 3/19102.
- 8. Technical Report NFS-1001A, Revision 5. Duke Power Company Oconee Nuclear Station Reload Design Methodology. January 2001.
0 OSC-8828 Rev. Page 41 RGC 02/25/2008 Appendix A
OSC 9771, Rev. 1 Drift Analysis for the RPS Reactor Coolant (RC) System Pressure
FIGURE 101 3 CERTIFICATION OF ENGINEERING CALCULATION - REVISION LOG CERTIFICATION OF ENGINEERING CALCULATION REVISION LOG Station And Unit Number Oconee Nuclear Station, Unit 1, 2, 3 Title Of Calculation Drift Analysis for RPS Reactor Coolant (RC)_System Pressure 0 (TS SR 3.3.1.5) Calculation Number OSC-9771 Active Calculation/Analysis [] YES LI NO Calculation Pages (Vol) Supporting Volumes ORIG CHKD Venr Appr' Issue Documentation (Vol) Meth. Date Rev. Revised Delet Aded Revised Deleted Added Deleted Added Date Date 1,2,3, Date Date No. IOther" Dat
,7,.. . I 1 ,,,*. '*I, '1,, __1,u .
1 - 1 1 ------------- -I4 - I -- t1 - 1 _ __ _I__ __ __ __ __ I ___ __ __ [ __ __ __ __ __ _ __ I ___ __ __ _ __ __ I __ __ _ __ _ __
- ____I __________ ____ ___ ___ ___ _____
NOTE 1: When approving a Calculation revision with multiple Originators or Checkers, the Approver need sign only one block. (6 Aug 2004)
FIGURE 101 ICERTIFICATION OF ENGINEERING CALCULATION CERTIFICATION OF ENGINEERING CALCULATION Station And Unit Number Oconee Nuclear Station, Units 1. 2 and 3 Title Of Calculation Drift Analysis for RPS Reactor Coolant (RC) System Pressure (TS SR 3.3.1 .5) Calculation Number OSC-9771 Total Original Pages i, I Through 47 Total Supporting Documentation Attachments 0 Total Microfiche Attachments 0 Total Volumes 1 Active Calculation/Analysis R YES E) NO Microfiche Attachment List El YES 91 NO If Active, is this a Type I Calculation/Analysis LI YES I] NO (SEE FORM 101.4) These engineering Calculations cover QA Condition 1 Items. In accordance with established procedures, the quality has been assured and I certify that the above Calculation has been Originated, Checked, or Approved as noted below: Originated By W. J. Brodbec4 Date Checked By "*." 19.-,a.p---, Date Verification Method: Method 1 Method 2 Method 3 Li 'W Other % Approved By___ . . . .Date _ Isue o CR:Date 11l D*7) Received By DCRM: Date Zr2 '1 ,
- Complete The Spaces Below For Documentation Of Multiple Originators Or Checkers Pages Through Originated By Date lChecked By Date Var! .o...
ILVerification .*..o..........-...M Method: .t.o..._....................e..h.o.....
. . . . . . . . I. . . . .r-1 Method Method 2 r-] ...........
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Form 101.2 (R3-03) Calculation Number OSC-9771 REVISION DOCUMENTATION SHEET Revision Revision Description Number 0 Original issue. 1 Editorial change to clarify that this analysis is also applicable to SR 3.3.1.5 Function 11, "Shutdown Bypass RCS High Pressure". The calculation covers the instrumentation for this SR and the SR is now clearly identified in Section 1.2.
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Engineering Manual 4.9 CALCULATION IMPACT ASSESSMENT (CIA) Station / Unit Oconee / 1.2.3 Calculation No. OSC-9771 Rev. 0 Page i PIP No. (if applicable) 0-09-4103 By W. 6 Date9A ir_ c* Prob. No. (stress & s/r use only) Checked By>.__ Date* J ,l" Note: A NEDL search is NOT required for NEDL reviewed to identify calculations? YES [ NO calculation originations (i.e. Rev. O's) (formally SAROS) Identify in the blocks below, the groups consulted for an Impact Assessment of this calculation origination/revision. Indiv. Contacted/Date Indiv. Contacted/Date [] RES El NGO (Power, I&C, ERRT, (QA Tech. Services (IS[), Reactor) Severe Accident Analysis,Elect. Sys. & Equip., Design & Reactor MCE Supp., Civil Structural, Core (Primary Systems, Balance of Mech. & T/H Analysis, Mech. Plant, Rotating Equipment, Sys. & Equip., Nuclear Design Valves & Heat Exchangers, and Safety Analysis, Civil) Matls/Metallurgy/Piping) El MOD (Mechanical Engr., Electrical El Training Engr., Civil Engr.) El Operations - m Local IT OPS Support El Regulatory Compliance El Maintenance - Tech. Support
-ChaiiiittWy- -- ____ - -
____ I- ---- _ Work Control - Program. Supp. [] Radiation Protection El Other Group yj No Group required to be consulted Listed below are the identified documents (ex: TECHNICAL SPECIFICATION SECTIONS, UFSAR SECTIONS, DESIGN BASIS DOCUMENTS, STATION PROCEDURES-, DRAWINGS, OTHER CALCULATIONS, ETC.) that may require revision as a result of the calculation origination or revision, the document owner/group and the change required (including any necesssary PIP Corrective Actions).
- Note: Any design changes, which require changes to Station Procedures, must be transmitted as Design Deliverable Documents.
DOCUMENT GROUP CHANGE REQUIRED PIP 0-09-4103, CA#2 NGO-SA The effect of the extended cycle Analyzed Drift on the RPS RC Pressure Total Loop Uncertainties (OSC-4048 & OSC-8828) should be evaluated. PIP 0-09-4103, CA#3 RES-DPS The effect of the extended cycle Analyzed Drift on the current RPS RC Pressure Channel Check acceptance criteria in PT/1,2,3/A/0600/001 should be evaluated. Page 1 of 1
Engineering Manual 4.9 1 A T CTT A rTnfl TIkXD A rCT A QQ~1PQQrI~1r3 11C! A1 Station / Unit Oconee / 1, 2, 3 Calculation No. OSC-9771 Rev. I Page ii PIP No. (if applicable) 0-09-4103 By W. J. Brodbeck Date I/It! Prob. No. (stress & s/r use only) Checked By .t Q Date 1/7/I NEDL reviewed to identify calculations? 3 YES Y Note: A NEDL search is NOT required for [ NO calculation originations (i.e. Rev. O's) (formally SAROS) Identify in the blocks below, the groups consulted for an Impact Assessment of this calculation origination/revision; Indiv. Contacted/Date Indiv. ContactedlDate D RES Li NGO (Power, I&C, ERRT, (QA Tech. Services (1SI), Reactor) Severe Accident Analysis,Elect. Sys. & Equip., Design & Reactor 11 MCE Supp., Civil Structural, Core (Primary Systems, Balance of Mech. & T/H Analysis, Mech. Sys. & Equip., Nuclear Design Plant, Rotating Equipment, Valves & Heat Exchangers, and Safety Analysis, Civil) Matls/Metallurgy/Piping) El MOD (Mechanical Engr., Electrical Li Training Engr., Civil Engr.) L] Operations - Local IT OPS Support EL Reaulatory Comptiance r El Maintenance - Tech. Support.--Ch LJ Chemistry Li Work Control - Program. Supp. LiRadiation Protection Li Other Group G/No Group required to be consulted Listed below are the identified documents (ex: TECHNICAL SPECIFICATION SECTIONS, UFSAR SECTIONS, DESIGN BASIS DOCUMENTS, STATION PROCEDURES-, DRAWINGS, OTHER CALCULATIONS, ETC.) that may require revision as a result of the calculation origination or revision, the document owner/group and the change required (including any necesssary PIP Corrective Actions).
- Note: Any design changes, which require changes to Station Procedures, must be transmitted as Design Deliverable Documents.
DOCUMENT GROUP CHANGEREQUIRED None - editorial changes only. Page 1 of 1
OSC-9771, Rev. 0 Page 1 TABLE OF CONTENTS Section Paue Number 1.0 STATEMENT OF PROBLEM/PURPOSE 2 1.1 RPS and ESFAS Replacement Program 3 1.2 Analyzed Instrument Loop Function 4 1.3 24 Month Cycle Extension Requirements 4 1.4 Instrument Locations And Installation Dates 5 2.0 RELATION TO OA CONDITION/NUCLEAR SAFETY 7 3.0 DESIGN CALCULATION METHOD 7 4.0 FSAR/TECHNICAL SPECIFICATION APPLICABILITY 11
5.0 REFERENCES
11 6.0 ASSUMPTIONS/DESIGN INPUT 13 6.1 Assumptions 13 6.2 Design Input/Bases 13 . 7.0 DRIFT ANALYSIS 15 7.1 Instrument Block Diagram 15 7.2 As-Found/As-Left Data Evaluation/Outlier Evaluation 16 7.3 Normality Tests/Bias Evaluation/Tolerance Intervals 24 7.4 Drift Data Time Dependency 30 7.5 Acceptable Limit (AL) Determination and Drift Data Comparison 37 7.6 Comparison of Analyzed Drift (ADE) with Uncertainty Calculation 38 Limits and Plant Procedure Acceptance Criteria
8.0 CONCLUSION
S/RESULTS 43 8.1 NRC GL 91-04 Issue 1 Resolution 44 8.2 NRC GL 91-04 Issue 2 Resolution 44 8.3 NRC GL 91-04 Issue 3 Resolution 45 8.4 NRC GL 91-04 Issue 4 Resolution 46 8.5 NRC GL 91-04 Issue 5 Resolution 46 8.6 NRC GL 91-04 Issue 6 Resolution 47 8.7 NRC GL 91-04 Issue 7 Resolution 47 Attachments Number of Pages None
OSC-9771, Rev. 0 Page 2 1.0 STATEMENT OF PROBLEM/PURPOSE The purpose of this calculation is to perform the As-Found/As-Left (AFAL) Drift Analysis for the Reactor Protection System (RPS) Reactor Coolant (RC) System Pressure instrument loops. This analysis is required to support ONS transition to 24 Month Fuel Cycles. The AFAL calibration data will be obtained through review of completed instrument procedures, IP/0/A/0305/001 M, IP/0/A/0305/001 N, IP/0/A/0305/001 0 and IP/O/A/0305/001 P (Reference 5.C). Per Reference 5.A and the NAS Electronic Database, the current loop tag numbers (of the applicable portions of the loop) are: UNIT 1 UNIT 2 UNIT 3 Channel A Channel A Channel A I RC PT 0017Pe') 2RC PT0017P 3 RC PT 0017P I RPS AF A20307(2 ) 2 RPS AF A20307 3 RPS AF A20307 O1A1688 02A1688 03A1688 Channel B Channel B Channel B I RC PT 0018P 2RC PT0018P 3 RC PT 0018P I RPS AF B20310 2 RPS AF B20310 3 RPS AF B20310 O1A1689 02A1689 03A1689 Channel C Channel C Channel C I RC PT 0019P 2RC PT0019P 3 RC PT 0019P I RPS AF C20310 2 RPS AF C20310 3 RPS AF C20310 O1A1690 02A 1690 03A1690 Channel D Channel D ChannelD I RC PT 0020P 2 RC PT 0020P 3 RC PT 0020P I RPS AF D20310 2 RPS AF D20310 3 RPS AF D20310 O1A1691 02A1691 03A1691 NOTES (based on current instrument loop configurations):
- 1) Rosemount Model 11 54GP9RB for all transmitters.
- 2) Bailey Model 6621670A for all buffer amplifiers.
OSC-9771, Rev. 0 Page 3 1.1 RPS and ESFAS Replacement Propram ONS transition to 24 Month Fuel Cycles was originally scheduled to be implemented after implementation of the ONS Digital RPS and ESFAS Replacement Project. However, due to implementation delays, the potential exists for 24 Month Fuel Cycles to be implemented before the Digital RPS and ESFAS Replacement is installed. The Digital RPS and ESFAS Replacement modifications will remove the original Bailey RPS and ESFAS instrumentation and replace it with equivalent digital instrumentation from AREVA, NP Inc. The new instrumentation includes all RPS and ESFAS hardware and software downstream of the sensors/transmitters. Typically, only the original sensors/transmitters will be retained. The Digital RPS and ESFAS modifications provide certification for all new instrumentation for calibration intervals up to a maximum of 30 months. From Section 9.3 of Reference 5.L:
"Specific TXS module operating history in terms of total module years and number of faults or failures were evaluated All the TXS modules mean time between failure (MTBF) observed data support a CHANNEL FUNCTIONAL TEST at an 18 month plus 25% interval by about two ordersof magnitude."
In addition, in Section 3.3.15 of Reference 5.L:
"Th- res-rlt- -fihT-h-dw--re--liibilityanais--7-s-l albi*
- supp-ort -- t7-ndifig-th*-.--
surveillance testing intervalfor channelfunctional tests to once per 18 months .... since the hardware availability analysis was based on assuming a 24 month surveillance testing interval." Therefore, an AFAL Drift Analysis is NOT required for those portions of an RPS and ESFAS System that have been replaced. In regard to instrument drift of the cabinet (rack) electronics; if implementation of 24 Month Fuel Cycles precedes the implementation of the Digital RPS and ESFAS, credit will be taken for the Channel Functional Test (TS SR 3.3.1.4 and TS SR 3.3.5.2 for the RPS and ESFAS, respectively). The same calibration steps, relative to the original Bailey RPS and ESFAS electronics, are performed during a Channel Functional Test as are performed during a Channel Calibration. The Channel Functional Test is performed on a more frequent basis than the Channel Calibration. Therefore, for that part of the loop, the Channel Functional Test fulfills the requirement of the Channel Calibration. See References 5.C and 5.J. Note that some RPS/ESFAS strings may serve multiple functions. An AFAL Drift Analysis may be required for those portions of the string that perform a non-RPS or ESFAS related function. The exclusion described above applies only to the instrumentation being replaced by the Digital RPS and ESFAS Replacement Modifications. See Reference 5.K.
OSC-9771, Rev. I Page 4 1.2 Analyzed Instrument Loop Function The RPS Reactor Coolant (RC) System Pressure Bistable string is used to initiate a reactor trip for the RCS High Pressure, RCS Low Pressure, RCS Variable Low Pressure and Shutdown Bypass RCS High Pressure functions. See Technical Specifications Section 3.3.1, Table 3.3.1-1, Functions 3, 4, 5, and 11, respectively. 1.3 24 Month Cycle Requirements The AFAL calibration data will be obtained through review of completed instrument procedures, IP/O/A/0305/001 M, N, 0 and P (see Design Input 6.2.1). These procedures are run on a Shutdown/Refueling interval, which currently is every 18 months with a 25% allowance (Reference 5.E). The 24 Month Fuel Cycle Program will increase this calibration interval to 24 months with a 25% allowance. NRC Generic Letter 91-04 (Reference 5.F) states that:
"Licensees must address instrument drift when proposing an increase in the surveillance interval for calibrating instruments that perform safety functions including providing the capability for safe shutdown. The effect of the increased calibration interval on instrument errors must be addressed because instrument errors caused by drift were considered when determining safety system setpoints and when performing safety analys es.
S Per Section 1.2, the RPS RC Pressure Bistable string is used to perform safety functions (TS 3.3.1, Table 3.3.1-1, Functions #3, 4, 5 & 11). Therefore, a drift analysis for RPS RC Pressure Bistable string is required to support cycle extension. The RPS RC Pressure strings are not used for safe shutdown and are not used to support any specific assumption of the Safety Analysis. The analyzed drift for the RPS RC Pressure OAC Indication, which is used for channel checks (Reference 5.D), will not be determined because these loops will be modified by Digital RPS and ESFAS Replacement. Therefore, it would not provide any additional meaningful data. (Note that the above 'requirements' for the RPS RC Pressure bistable strings are subject to the Digital RPS and ESFAS Replacement exclusions described in Section 1.1. The exclusions will be discussed further in Section 1.4.) This drift evaluation will be performed in accordance with NRC Generic Letter 9t1-04 and the ONS Instrument Drift Analysis Methodology (References 5.F and 5.G, respectively). The Drift Analysis Methodology is summarized in Section 3.0.
OSC-9771, Rev. 0 Page 5 1.4 Instrument Locations And Installation Dates Instruments strings with similar models, environment and function may be grouped into a single AFAL sample population (Reference 5.G). From Reference 5.A: The RPS RC Pressure Bistable strings currently consist of a pressure transmitter, a buffer amplifier and three bistables (per string). See Figure 7.1-1. The RPS RC Pressure OAC Indication strings currently consist of a pressure transmitter, a buffer amplifier and OAC input module (Reference 5.A.a). The buffer amplifier and the bistable will be replaced as part of the ONS Digital RPS and ESFAS Replacement Project. As stated in Section 1.1, prior to implementation of the RPS and ESFAS Replacement Project, the more frequent Channel Functional Test will be credited in regard to the drift of the buffer amplifier and bistable. The signal to the OAC will be provided by a digital gateway from the new digital RPS (Reference 5.A.b). Therefore, only the RPS RC Pressure transmitter is available for and requires an AFAL Drift Analysis. All other instrumentation is accounted for as part of the Digital RPS and ESFAS Replacement modifications as is explained in Section 1.1. Per Reference 5.C, the buffer amplifier is included in the calibration of RPS RC Pressure transmitter. This is conservative but is not expected to have a significant effect on the transmitter analyzed drift (Assumption 6.1.3). A review of the History Section of NAS Electronic Database for buffer amplifier was made to determineifany-buffer-amplifier-cards-were-repaired-or-replaced-mid=cycle---Only one example of a buffer amplifier being replaced was found (WO # 1578811) and this replacement occurred during an outage. Therefore, its effect on the transmitter AFAL drift data will be expected to be minimal. To facilitate proper grouping of AFAL data, a history of models used in the RPS RC Pressure transmitter over the analysis period is required. The earliest AFAL data used in this analysis is from 4/8/1998 (see Section 7.2 and Design Input 6.2.1). The EQ install dates predate the earliest AFAL Drift Analysis date; therefore, the transmitter models throughout the AFAL data collection period are as shown below.
OSC-9771, Rev. 0 Page 6 CURRENT PREVIOUS Model & Install DateM) Model & Install Date0') 1RC PT0017P: Rosemount 1154 < 4/98 1RC PTOO18P: Rosemount 1154 < 4/98 1RC PT0019P: Rosemount 1154 < 4/98 1RC PT0020P: Rosemount 1154 < 4/98 2RC PTOO17P: Rosemount 1154 = 11/99 Rosemount 1154 < 4/98 2RC PTOO18P: Rosemount 1154 = 11/99 Rosemount 1154 < 4/98 2RC PTOO18P: Rosemount 1154 = 11/99 Rosemount 1154 < 4/98 2RC PT0020P: Rosemount 1154 < 4/98 3RC PTOO17P: Rosemount 1154 < 12/98 Rosemount 1154 < 4/98 3RC PTOO18P: Rosemount 1154 < 4/98 3RC PTOO19P: Rosemount 1154 < 4/98 3RC PT0020P: Rosemount 1154 < 5/03 Rosemount 1154 < 4/98 Notes: 1) Based on NAS Electronic Database and Design Input 6.2.1. From References 5.A and 5.C: All transmitters have the same function (i.e., - measure-RC--System-pressure-)T-the-transmitters- are-located-in-similar-locations-(i.e., 2 nd Level Reactor Building) and have the same range and span. However, certain transmitters were used to fulfill the Low Temperature Over-Pressure (LTOP) requirements. See TS Section 3.4.12. LTOP now has dedicated transmitters and no longer requires RPS RC Pressure transmitter input; however, during the AFAL data collection period, one channel per unit was re-calibrated before each outage (planned or. forced) to serve as a pressure input to the LTOP System. These transmitters were 1RC PT0019P, 2RC PT0018P and 3RC PT0017P (Reference 5.1). It should be noted that the RPS RC pressure transmitters for LTOP were not recalibrated under the same conditions as the other RPS RC Pressure transmitters. The as-found data was taken while the unit was at power and the reactor building was at a significantly higher temperature. Therefore, data for the LTOP related transmitters will not be included in this drift analysis because this data is not representative of the performance expected for RPS RC Pressure transmitters in the future. See Assumption 6.1.2 and Section 7.2. All other Rosemount 1154 transmitter AFAL data (defined by Design Input 6.2.1) may be grouped into a single sample population.
OSC-9771, Rev. I Page 7 2.0 RELATION TO OA CONDITION/NUCLEAR SAFETY This calculation was designated a QA Condition 1 Calculation as the Reactor Protection System Reactor Coolant System Pressure instrumentation is relied upon to trip the reactor during certain design basis events. The Reactor Coolant Pressure trip setpoints are defined in Technical Specification Section 3.3.1, Table 3.3.1-1, Functions 3, 4, 5 and 11. 3.0 DESIGN CALCULATION METHOD This methodology provides the guidance required to perform a drift analysis using the historical As-Found/As-Left (AFAL) instrument calibration data. This methodology is based on the ONS Instrument Drift Analysis Methodology and EPRI Report TR-103335-RI (References 5.G and 5.H, respectively). As-Found/As-Left Data The initial step in the AFAL Drift Analysis is the gathering of the as-found/as-left data from completed plant calibration procedures. In addition to the AFAL data, sufficient reference information (such as, work order numbers, tag numbers, etc.) should also be documented to provide complete traceability. From the AFAL data, a raw drift will be calculated as follows: DRAw. = {AF. - AL- 1}/span Where: DRAwn = Drift between "n" and "n-l" calibrations AF,, = As-found data for calibration "n" AL(,_-) = As-left data for calibrations "n-I" span = Instrument calibrated span. Acceptable Limits The raw AFAL data is subject to the following NRC Generic Letter 91-04 constraint; that it has not, except on rare occasions, exceed acceptable limits. To determine an Acceptable Limit (AL), at a minimum, the accuracy and drift of all instruments in the string should be combined along with the errors for the M&TE equipment used to calibrate the string/loop: AL = +/- [ATR2 + ASC2 + AIN2 + DTR2 + Dsc 2 + DIN2 + MTE2 + RES 2]1'2
OSC-9771, Rev. 0 Page 8 Note that this example calculation assumes a loop consisting of a transmitter (TR), signal conditioning module (SC) and an indicator (IN) is being calibrated and that the indication display (RES) will be used as part of the calibration. In certain cases additional terms, such as, known temperature effects, static pressure correction errors, etc. may also be considered. AFAL data will be deemed to have failed the initial GL 91-04 constraint when more than 5% of the raw drift values exceed its Acceptable Limit. Failure to meet the Acceptable Limit should be investigated on a case by case basis in consultation with the appropriate System Engineers. Initial Statistics The initial statistics determined are the mean (average), median and standard deviation of the sample population. The sample mean is determined using the following: ZD,
=1 n Where: n = number of drift terms.
n If there are an odd number of data points, median is the middle number in an ordered set ofata_.* f*-here is an even number of-d-ta --poi-ft-,the medi*an-i-the average of the two middle data points in an ordered set of data. The sample standard deviation value is calculated using the following:
=2 E(D, I)2 G (n-i) Where: n = number of drift terms.
Microsoft Excel's AVERAGE, MEDIAN and STDEV functions may be used to calculate the mean, median and standard deviation-of the sample population. A mean, median and standard deviation of the drift sample population should be calculated at each calibration point, typically 0%, 25%, 50%, 75% and 100% of span. However, the combined-point method (i.e., combining the data of two adjacent calibration points) may be used wherever the point of interest is in between calibration points.
OSC-9771, Rev. 0 Page 9 Outlier Testing Outlier testing, as described in the Outlier Analysis Section of Reference 5.G, should be performed on the raw data. A single outlier may be removed from the sample population based solely on the T-Test. Justification for removal of additional outliers/erroneous data shall be documented. Examples of this justification are instrument failures, obvious transcription errors, M&TE malfunctions, etc. After removal and documentation of all outliers, the final sample data statistics should be recalculated. Tolerance Intervals After final sample data statistics are determined, the sample mean should be tested for evidence of a bias in the sample distribution as described in the Drift Bias Determination Section of Reference 5.G. If the sample mean is determined not to represent a bias in the analyzed drift, the sample mean is considered negligible in all subsequent calculations. The tolerance interval is calculated as follows: TI = +/- (TIF 9 5/95 x F). Where: TI = tolerance interval and TIF 95/ 95 = tolerance interval factor from Table 4.2 of Reference 5.G (for a 95/95 confidence level). Note that if sample mean was determined not to represent a bias, then the sample mean (Pi) in the above formula would be considered zero. Normality Testing The D-Prime or W-Tests (depending on sample size) should be used to determine if the sample data is inconsistent with a normal distribution (to a 5% significance level). These tests are described in detail in References 5.G and 5.H. If the sample distribution is considered normal, then the Tolerance Interval calculated - above is to be used as the 18 month Analyzed Drift (AD) term. If the distribution is considered non-normal, then a new Tolerance Interval/Analyzed Drift term based on Coverage Analysis is to be determined as follows: AD = TI = - (TIF 95/95 x a x NAF). Where: NAF = normality adjustment factor. The NAF is chosen such that a minimum of "(n - 1)/n" or 97.5%, whichever is less, of all sample data (n) is covered by the above tolerance interval. For further details see the Normality Testing Section of Reference 5.G. Note that if sample mean was determined not to represent a bias, the sample mean (ji) in the above formula would be considered zero.
OSC-9771,Page Rev. 0 10 Time Dependency Time dependency is either considered negligible, moderate or strong. If the bias portion of the Analyzed Drift is determined to be negligible (as discussed above), its time dependency is also be considered negligible (i.e., the bias remains zero). Otherwise, the bias portion of the extended calibration interval Analyzed Drift (ADE-BIAS), whether moderate or strongly time dependent, is determined as follows:
= X CIE ADE.BIAS ClO Where CIE = length of extended calibration interval and CIO = length of the original calibration interval.
For the random portion of the Analyzed Drift, the characterization of time dependency as either moderate or strong is based on the ratio of the multi-cycle standard deviation to the single cycle standard deviation. If the ratio is less than or equal to the square root of the average multi-cycle calibration interval divided by the average single cycle calibration interval (referred to as the critical ratio), the original assumption of moderate time dependency is retained and the random portion of the extended calibration interval analyzed drift (ADE-RANDOM) is determined as follows: ADE-RANDOM = ADRANDOM-- C-
"*CIO 0Where: CIE is the extended cycle calibration interval (i.e., 30 months) and CIO is the average calibration time interval from the sample data.
If the ratio is greater than the critical ratio, the time dependency is considered strong and the random portion of the extended calibration interval analyzed drift (ADE-RANDOM) is determined as follows: ADE-RANDOM = ADRANDOM X CIE. Final Analyzed Drift Terms The final extended cycle analyzed drift term is the combination of the appropriate bias and random portions as determined above. ADE = ADE-RANDOM +/- ADE-BIAS The extended cycle analyzed drift terms may be used in the instrument uncertainty calculations in accordance with EDM-102 (Reference 5.B.a). The extended cycle analyzed drift may be used to account for all the components that were included in the Acceptable Limit term. I ___ __ -
OSC-9771, Rev. 1 Page 11 4.0 FSARITECHNICAL SPECIFICATION APPLICABILITY 4.1 Units 1, 2 & 3 Oconee UFSAR, Sections 7 and 15. 4.2 Technical Specifications, TS Section 3.3.1 (Table 3.3.1-1, Functions 3, 4, 5 and 11), SR 3.3.1.5 and TS Section 3.4.12.
5.0 REFERENCES
A. a) OSC-4048, Revision 5, "RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses, and Variable Low Pressure Safety Limit" Calculation. b) OSC-8828, Revision 2, "Digital RPS RCS Pressure & Temperature Trip Function Uncertainties and Variable Low RCS Pressure Safety Limit" Calculation. B. a) EDM-102: Instrument Setpoint/Uncertainty Calculations, Revision 3. b) ISA-$67.04, Part I, Setpoints for Nuclear Safety-Related Instrumentation, Approved September 1994. c) ISA-RP67.04-Part 11-1994, Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation, Approved September, 1994. C. Oconee Procedure for Reactor Protection System Channel A/B/CID RC Pressure Instrumentation Calibration:
- Channel A: IP/0/A/0305/001 M, Revision 71,
- Channel B: IP/0/A/0305/001 N, Revision 67,
- Channel C: IP/O/A/0305/001 0, Revision 58.
- Channel D: IP/O/A/0305/001 P, Revision 58.
D. Oconee Periodic Surveillance:
- Unit 1: PT/1/A/0600/001, Revision 308, e Unit 2: PT/2/A/0600/001, Revision 286,
.. ........ Unit-3: PT/3/A!0600/001, Revision 288.
E. RPS Reactor Coolant System Pressure Instrument Calibration Model Work Order Numbers: *
- Unit 1: 01459021, 01459023, 01459025 & 01459027,
- Unit 2: 01459296, 01459298, 01459300 & 01459302, a Unit 3: 01459520, 01459522, 01459523 & 01459524.
~1 OSC-9771, Rev. 0 Page 12 F. NRC Generic Letter 91-04, Dated: April 2, 1991, "Changes In Technical Specifications Surveillance Intervals To Accommodate A 24-Month Cycle".
G. OSC-9719, Revision 1, "Instrument Drift Analysis Methodology in Support of 24 Month Surveillance Interval". H. TR-103335-R1, Dated October 1998, "EPRI Guidelines for Instrument Calibration Extension/Reduction -- Revision 1: Statistical Analysis of Instrument Calibration Data".
- 1. Oconee Instrument Procedure for Reactor Protective System Pressure Transmitter Range Change For LTOP Backup Indication, IP/0/A/0305/001 Q, Revision: deleted.
J. NI/RPS Calibration And Functional Test Procedures:
" Channel A: IP/1/A/0305/003 A, Revision 104, IP/2/A/0305/003 A, Revision 101, IP/3/A/0305/003 A, Revision 111,
" Channel B: IP/1/A/0305/003 B, Revision 105, IP/2/A/0305/003 B, Revision 108, IP/3/A/0305/003 B, Revision 103,
" Csnannel C: 117AIIA/0U305/003 C, Kevislon 105.
IP/2/A/0305/003 C, Revision 105. IP/3/A/0305/003 C, Revision 106.
" Channel D: IP/1/A/0305/003 D, Revision 114.
IP/2/A/0305/003 D, Revision 109. IP/3/A/0305/003 D, Revision 116. K. Digital RPS and ESFAS Replacement Project Modifications: RPS ESFAS
" Unit 1: EC 0000090482 EC 0000090423
" Unit 2: EC 0000077068 EC 0000077067
" Unit 3: EC 0000077070 EC 0000077069 L. Oconee Nuclear Station Digital RPS/ESPS License Amendment Request 2007-09, dated January 2008 (Proprietary).
M. a) OSC-8695, Revision 4, "Unit 1 Software Parameters for TXS Plant Protection System". b) OSC-8612, Revision 0, "Unit 2 Software Parameters for TXS Plant Protection System". c) OSC-8610, Revision 0, "Unit 3 Software Parameters for TXS Plant Protection System".
OSC-9771, Rev. 0 Page 13 6.0 ASSUMPTIONS/DESIGN INPUT 6.1 ASSUMPTIONS 6.1.1 The Analyzed Drift determined in this analysis has moderate time dependency unless demonstrated otherwise. This is a standard assumption of Reference 5.G. 6.1.2 The RPS RC Pressure transmitters that are used for LTOP Backup Indication are calibrated at different environmental conditions than the rest of the RPS RC Pressure transmitters. Therefore, the AFAL drift data for the transmitters that are used for LTOP Backup Indication are not representative of the performance of the RPS RC Pressure transmitters. See Note 5 of Table 7.2-4. 6.1.3 The AFAL drift data for the transmitter and buffer amplifier combination is conservative for use as the transmitter only AFAL drift data. Per Reference 5.C, the buffer amplifier is included in the calibration of RPS RC Pressure transmitters. Per Section 1.1, the buffer amplifier is being replaced as part of the RPS/ES Replacement Program. Per Section 7.5.1, the accuracy for the transmitter is larger than the accuracy for the buffer amplifier and the drift for the transmitter is larger than the drift for the buffer amplifier. Therefore, the transmitter uncertainties will dominate the AFAL performance of the transmit-te/1biffer -amplifiercomb-naltion. Th-F&sltill-be a conservativ--eAF-L drift value that does not mask the performance of the transmitter (i.e., normality, time dependency, etc.)
OSC-9771, Rev. 0 Page 14 6.2 DESIGN INPUT/BASES 6.2.1 The Reactor Building Narrow Range Pressure AFAL Drift Analysis is based on the completed instrument procedures for IP/0/A/0305/001 M, IP/0/A/0305/001 N, IP/O/A/0305/001 0 and IP/0/A/0305/001 P (Reference 5.C) and IP/0/A/0305/001 Q (Reference 5.1) performed under the following Nuclear Asset Suite (NAS) work order numbers: Unit 1 Unit 2 Unit 3 1768640 1610276 1679918 1556663 1740601 1601293 1767936 1610275 1679917 1556661 1740598 1601292 1767935 1578812 1679916 1556660 1740582 1565768* 1767934 1578811 1679915 1556659 1740580 1565645 1670439 1578810 1652931 1525092 1662470 1565644 1670438 1578809 1652930 1525091 1662469 1565643 1670437 1544109* 1652929 1525090 1662468 1565642* 1670436 1543963 1652928 1525089 1662467 1535189 1670201* 1543962 1623409 1514175* 1634196* 1535187 1643665 1543961 1623408 1495206 1633338 1535186 1643664 1543960 1623407 1495205 1633337 1530188 1643663 1515825 1623406 1495204 1633336 1503594 1643662 1515824 1590531 1495203 1633335 1503593 _ _1-6--161'70*-1-515823-1-590530F 1616623*-1503592 1610278 1515822 1590529 1601295 1503591 1610277 1590528 1601294
- Non-PM Reference 5.C Work Orders.
These Work Orders are primarily PM calibrations performed -using the subject instrument procedures. Typically, the PM calibration data is readily accessible though NAS. For non-PM work on this instrumentation (i.e., corrective, modification, etc.), NAS along with the EDB was used to the extent possible to find instances affecting the "calibration data string" for the loops. Although total coverage cannot be assured there is high confidence that the aggregate of the data retrieval and documented above is representative of the historical loop performance. 6.2.2 The calibration intervals are based on an average of 30.44 days per month (=-365.25 + 12).
OSC-9771, Rev. 0 Page 15 7.0 DRIFT ANALYSIS The calculation is organized as follows: Sections 7.1 contains a Block Diagram of the applicable RC pressure instrumentation; Section 7.2 contains Raw AFAL Data and Outlier Evaluation; Section 7.3 contains the Normality Tests, Bias Evaluation and Tolerance Intervals; Section 7.4 contains the Time Dependency Evaluation; Section 7.5 determines the Acceptable Limit (AL) and compares the AL to the AFAL data; and Section 7.6 compares ADE with the uncertainty calculation 30 month limits and compares ADE with the 18 month plant procedure acceptance criteria. 7.1 Instrument Block Diagram Figure 7.1-1 shows a block diagram of the current Bailey instruments. The TELEPERM ES/RPS Upgrade will replace all the instruments except for the transmitters. This upgraded instrumentation will be designed for a 24-month fuel cycle and; therefore, is not applicable to this analysis (see Section 1.1 and Reference 5.A.b). Only the analyzed drift for the Rosemount 1154 will be determined for this application. See Assumption 6.1.3. FIGURE 7.1-1 INSTRUMENT BLOCK DIAGRAM 503 Ohm BUFFER TRANSMITTER Resistor AMPLIFIER BISTABLES Figure 7.1-1 is based on OM 201.K-0012, Revision DL and OM 201.K-0015, Revision DF for Unit 1, Channel A. Loops for other units and channels are similar.
OSC-9771, Rev. 0 Page 16 7.2 As-Found/As-Left Data Evaluation/Outlier Evaluation Per Section 1.1, 1.3 and 1.4, only the Rosemount 1154 transmitter through buffer amplifier string requires an AFAL Drift Analysis. Section 1.4 also shows that those transmitters used as backup LTOP Indication should not be included in the sample data. This issue will be explored further in Section 7.2.1. 7.2.1 Transmitter String Raw AFAL Data/Outlier Evaluation The initial statistics for non-LTOP related RC Pressure transmitters are shown below in Table 7.2-1. The initial statistics for LTOP related RC Pressure transmitters are shown below in Table 7.2-2. The raw AFAL data taken from the completed calibration procedures are shown in Table 7.2-4 (see Reference 5.C and Design Input 6.2.1). The raw AFAL data has been converted to units of "% of span" in Tables 7.2-1 and 7.2-2. The average calibration interval for the statistics in Table 7.2-1 is 18.0 months. Table 7.2-1 RPS RC Pressure non-LTOP Transmitter Initial Statistics Calibration Point 1700 psig 1900 psig 2100 psig 2300 psig 2500 psig n 54 54 54 54 54 (1) Mean= 0.181% 0.196% 0197% 0164% 0.116% (2) Median = 0.035% 0.085% 0.130% 0.050% 0.115% (2) Standard Deviation = 0.556% 0.567% j 0 584% 0.621% 0.650% (2) Maximum Value[ 2.31% 2.15% 2.13% 1 2.10% J 1.86% 1(3) Minimum Value =1 -0.75% -1.02% -1.54% 1 -2.20% 1 -2.53% 1(4) calculated T value = 3.83 3.45 3.31 3.81 4.07 (s) Critical T value = 3.37 3.37 3.37 3.37 3.37 (6) outlier outlier okay outlier outlier Notes 1) Number of data values per calibration point in Table 7.2-4 (for non-LTOP transmitters).
- 2) Mean (pa), median and standard deviation (a) of the data values for each calibration point in Table 7.2-4 (for non-LTOP transmitters). As calculated by Microsoft Excel's AVERAGE, MEDIAN and STDEV functions.
- 3) Most positive data value for each calibration point in Table 7.2-4 (for non-LTOP transmitters).
- 4) Most negative data value for each calibration point in Table 7.2-4 (for non-LTOP transmitters).
- 5) Calculated T value I (V - I/)I/a. Where: V is the minimum or maximum value.
- 6) Linearly interpolated from Table 4.1 of Reference 5.G for an Upper 1%
Significance and n = 54.
OSC-9771, Rev. 0 Page 17 The average calibration interval for the statistics in Table 7.2-2 is 13.6 months. Table 7.2-2 RPS RC Pressure LTOP related Transmitter Initial Statistics Calibration Point = 1700 psig 1900 psig 2100 psig 2300 psig 2500 psig n= 22 22 22 22 22 IM Mean = -0.269% -0.222% -0.288% -0.308% -0.192% (2) Median = -0.185% -0.190% -0.180% -0.210% -0.130% (2) Standard Deviation = 0.469% 0.610% 0.607% 0.566% 0.566% (2) Notes 1) Number of data values per calibration point in Table 7.2-4 (for LTOP transmitters).
- 2) Mean (p), median and standard deviation (a) of the data values for each calibration point in Table 7.2-4 (for LTOP transmitters). As calculated by Microsoft Excel's AVERAGE, MEDIAN and STDEV functions.
The purpose of the data in Table 7.2-2 is to support the assumption that the AFAL drift data for the transmitters that are used for LTOP Backup Indication are not representative of the expected extended cycle performance of the RPS RC Pressure transmitters (Assumption 6.1.2). The RPS RC Pressure transmitters that are used for LTOP Backup Indication are calibrated at different environmental conditions than the rest of the RPS RC Pressure transmitters. By inspection of Tables 7.2-1 and 7.2-2, while the standard deviations are similar, the means and medians are signiificantly different. In addition, the average calibration intervals are significantly different. Therefore, the data in Table 7.2-2 and the average calibration interval supports the discussion in Section 1.4 and Assumption 6.1.2 that the AFAL data for the RPS RC Pressure transmitters that also served as LTOP transmitters is not applicable to future RPS RC Pressure transmitter performance. See Assumption 6.1.2. The AFAL data for the RC Pressure transmitters that also served as LTOP transmitters will not be Used to determine the tolerance intervals or analyzed drift terms for the RPS RC Pressure transmitters, which were not used as LTOP transmitters. The initial statistics for the Non-LTOP Related Transmitters in Table. 7.2-1 shows. a number of outliers. Most significantly for loop 3RC PT0020P, which during a period from 11/16/2004 to 5/12/2006, had its transmitter replaced twice for poor performance. See Table 7.2-4. The data during this period is not considered representative of the typical loop performance, which is the reason the transmitters were replaced. Reference 5.G allows removal of data for failing instruments: - Reference 5.G also allows one outlier t- be rrmoved fr -purely statistical reasons. The final statistics for the RPS RC Pressure transmitters, with the AFAL outlier data described above removed, are shown in Table 7.2.3.
OSC-9771, Rev. 0 Page 18 Table 7.2-3 RPS RC Pressure Transmitter Final Statistics Calibration Point = 1700 psig 1900 psig 2100 psig 2300 psig 2500 psig n= 52 52 51 51 51 :l) Mean = 0.103% 0.124% 0.161% 0.141% 0.106% (2) Median = 0.025% 0.065% 0.130% 0.040% 0.110% (2) Standard Deviation = 0.392% 1 0.437% 7 0.416% 0.412% 0.455% (2) Maximum Value = 1.04% 1.29% 1.36% 1.30% 1.42% (3) Minimum Value = -0.75% -1.02% -0.73% -0.70% -0.95% 1(4) Notes 1) Number of data values per calibration point in Table 7.2-4 (for non-LTOP transmitters).
- 2) Mean (gi), median and standard deviation (a) of the data values for each calibration point in Table 7.2-4 (for non-LTOP transmitters). As calculated by Microsoft Excel's AVERAGE, MEDIAN and STDEV functions.
- 3) Most positive data value for each calibration point in Table 7.2-4 (for non-LTOP transmitters).
- 4) Most negative data value for each calibration point in Table 7.2-4 (for non-LTOP transmitters).
Work Order Calibration Raw AFAL Data 28 . CalibrationAFAL Drift Values4) Number Date (i) - 0.111 V 2.389 V 4.889 V 7.389 V 9.889V Interval(3) 1700psig 1900psig 2100psig 2300psig 2500psig
*I. I - - - F - g 8R7 I IPIl/A/03051001 M AL]t -n100 I2 395 14 903 1 7 400 Enclosure 11,3.1 &
1767934 4116/2008 AF: -0107 2.44 1 T695 431820 0.03% 0.49% 0.60% 0.1 % 0. 11.5.1 AL -0110 2.395 4.885 7395 9.884 1 - 04% 4 1670436 AF*I -0 149 2 3S4 4 831
- 7 3381 9 840 931 7 ý338 984U 17.58 -0.38% -0.41% -0.73% -0.57% I .0.55%
1RC PT0017P AL:I -0.111 2.395 4.904 7.3951 9.895 1643662 4/23/2005 2nd Level RB AF7 -0.111 2.395 4.904 7.395 I 9.895 18.36 -0.08% -0.02% 0.14% -0.04% 0.05% AL: .0.105 2.397 4.890 7.399 9.890 1610275 1RPSAFA20307 AF: -0.040 2.474 4.965 7.446 I 9.923_ 1817 100% 087% 0.73% 0.60% 0.45% RPS Cabinets 1578809 4/72002 AL: AF: -.-0.140 14 2.387 2.387 4.892 7.386 II 9.878 AF: -0.140 2,387 4.8982- 7.380 9.68 2 1620 -020% 002% 011% 0.06% 0.10% 1543960T AL: -0.120 2.385 4.881 7.3801 9.866 AF -0.120 2.382 4.881 7.380 1 9.868 1794 -013% -0.03% -0.07% .0.11% 1 4-AL 0107 2.32 4884 7.387 1I 9.879 ___ ____ 1515822 6/311999 AF:, -0.107 2.382 4.884 1 7.387 9.879 IPI2JA/0305/001 M AL:1 -0.103 2.390 4.902 7.409 I , 9.902 1679915 5/18/2007 Enclosure 11.3.2 & AF:I -0.103 2.390 4.902 7.409 I 9.902 CD 18.33 -0.07% -0.22% -0.04% 1 0.01% 1 -0.13% 11.5.2 AL: -0.096 2.412 4.906 7.408 9.915 (D 1652928 11/6/2005 -. 4 - - i -4 4 4.-4 4 4-AF:l -0.105 2.390 4.876 7.386 9.906
, - -.. .. . . ... . ... . 17.87 . -0.07% -0.18% -0.31% -0.18% -0.02%
2RC PT0017P AL: -0.098 2.408 4.907 7.404 I 9.908 a-CD 2nd Level RB 1623406 5/1112004
. A- , -- -007 . - 3 4 2.436 4 4.937 7.445 I 9.948
- .- 18.07 0.11% 0.26% 0.19% 0.31% 0.25%
AL:- -0.084 2.410 4.918 7.414 I 9.923 2RPSAFA20307 1590528 11/8/2002 AF:1 -0.084 I 2.410 4.918 7.414 9.923 RPS Cabinets . .. - .... ..... 18.27 0.10% 0.08% 0.13% -0.01% 0.02% 7.415 1 19.921 0 0 Transmitterreplaced 1556659 4 J5/1/2001 AL:) AF: 4-# AL:I
-0.094
-0.094 37.4
-0.112 I 2.402 4:
I I 2.402 117 I 2.404
.. . 4 4
4.905
. 1..
4.905 XII 4 4-7'15 1 7.416 9,921 -4 910 17.61 4-1-4-4 0.18% -0.02% 0.03% -0.01%
.4-0.11%
=1 during WO# 1525089 4.908 1525089 11/12/1999 PM. AF:I -0.009 2.499 5.014 7.540 1 110.038 19.09 4 t-~-,.4 -. 4 --- 4- 0.84% 0.84% 0.80% 1.23% 1 1.06% AIA -0.093 24 7.417 9 932 1495203 41/10/1998 AFj-0.044 12F' .. 4 4
- ..... .... 4 i t9' 41 7.414 9.921
-4) 901 IP/3/A/0305/001 M Enclosure 11.3.3 &
11.5.3 1740580 1662467 12/3/2007 AL: 10/28/2007 4/29/2006 A77 -0.132 AL AF
-0.103
-0.104
-0.134-2.408 2.370.
2,400 2.376 4.906 4.870 4.900 4.873 7.408 7.370 7.404 1 7.378 I 9 880 9,686! 17.97. 16.08 I,-___j0.28'/0
-0.36%
-0.30%
-0.26%
0
-0.30%/
-0.47%
-0.34%
-0.23%
J-0.06%
-0.36%
15) (s) 3RC PT0017P 1634196 12/26/2004 AL: -0.098 2.402 4.920 7.401 1 10/9/2004 AF -022 2.209 4.669 7.200 4-4-4 4 1--I - 2nd Level RB -1.56% -1.92% -2.31% -2.03% -1.99% 15.90 1616623 6/13/2003 AL: -0.096 2.401 4.900 7.403 1 3RPSAFA20307 1601292 4/26/2003 A3 -0.130 12.378 4.886 7 i393 16.46 j -0.10% -0.38% -0.35% -0.26% 0.39% (5) 0 RPS Cabinets -0.120 2.16 4.921 7. 1 1565642 12/11/2001 AL ..... i 1565642 11/10/2001 AF: -0.114 2.408 4.895 7.404 I 9.889 664 -0.15% 0.07% -0.22% 0.01% -012% PM for WO# 1633335 9.901 1565768 4/22/2001 AL -0099 2401 49 74031 0.03_ - 0 -0__ -0__ 15)" is with WON 1634196. 156.5768 2/17/2001 AF -0.098 2.403 4.90 7.385 I 15316511612000 516200 A.0 L: -0.101 2.40 05 4.0
-90 7-402 99005 9.10 0.03% -0.02% 0.01% -0.17% -0.25%
, 4113/2000 AF: -0.12 2.391 Q-. J 4
2.410 4.907 16.26 -0.20% .0,19% -0.17% -0.16% -0.11% (sa" - 11 0.0092 I I 7.407 I I 9.894 150,3591 12/5/1998 I \O< AF' n~w trnnmuft*ri AF: ....... qmitte........
0 Work Order Calibration Raw AFAL Data (z) Iibio AFAL Drift Values pq Number Date () .0.111 V 2.389 V 4.889 V 7.389 V 9.889V Interval(3) 1700 psig 1900 psig 2100 psig 2300 psig 2500 psig IP/M/A03051001 N 4.894 7.410 1767935 4/1612008 AL: -0.090 2.407 T-9-85-6-1 9.2 Enclosure 11.3.1 & AF: -0.17 .342 4.844 7.335 11.5.1 2 .2 18.20 0.13% 0.30% 0.66% 0.37% 0.32% 1670437 10/10/2006 ALL -0.094 2.407 4.904 7.402 9.0 _____ AF:_-0.175A2:34 4.844 7.335 105 175 03 -0.1% -0.70% -.084% 1RC PT0018P -0.100 M 2.405 44905 7,405 9905.07%g 0.3 16431663 4/23/2005 -AL: 2nd Level RB
- - AL: -0.100 2.415 495 7405 9.905~- 18.36 0.010% -010% -0.11% -0.14% 0.01%
1810278 10/1212032- 0000 2415 4,96 7-19 -. 9-1RPSAFB20310 - ________ AF: -0.075 2.447 4.950 7.450 1 921 87 02 2% 09 3% 03 RPS Cabinets 7.413 1 ,!29908 .7 1 .2 .5% 1 02% 0.7 .3 11578810 4/7/2002 AL: -0.087 1 2.422 4.921 _____AF: .0.087 1 2.4I22 491 741ý3 I 9908 116.20 1 0.02% 0.04% 10.11% -0.01% 0.00% 1543981 11/30/2000 L: .0.085 21 910 741!Z 98____ ___ AF:- -010 49 49 48 .7- 17.94 -0.07% 0.025% -0.19% -0.14% -0.22%
- AL, -0.102 1 2.415 1 4.910( 7402 1 9.892-1 1515823 613/1999 ... i:- : i : : L _ _
AF:1 -0.102 2.415 1 4.910 1 7.402 9.892 IP/2/N0305/001 N AL! -0 090 2 400 4 915 7 413 I 9.905 c/) 1679916 4/28/2007 AIJ) -0090 1 2400 1 4915 7413 i990 Enclosure 11.3.2 & AF:1 -0.119 1 2.420 1 4.920 7.409 I 9.909 0.08% 0.36% 18.17 0.18% 0.24% 0.29% 11.5.2 AL:H -0.137 1 2.398 1 4.891 i 7.401 9.873 1852929 10/22/2005 . . " ... . i ... .. . . + t 1 - 2RC PT0018P 1623407 1623407 3/2W2004 6/2/2004 AF:1 AF:I AL:I
-0.186
-0.109
-0.129 1
1I 2,350 2.380 2.392 I 1 1 4.863 4.897 4.898 I 7.364 7.400 I 9.855 I 1 9.888 16.66 -0.57% -0.42% -0,35% -0.36% J 0 (5) C*1 z 2nd Level RB
- 3/20/2004 AF: 1 -0.109 1 2.380 1 4.897 7.362 I 1 9.845 15.97 -0.01% -0.16% -0.17% -0.32% -0.38% j,)
1590529
-1590529 11/20/2002 AL: -0.108 1 2.396 4.914 7.394 I 1 9.883 s) 2RPSAFB20310 AE. I rtt - 4.822 98333 9.819 1 18.52 -0665 -079% -0.78% -060% -080%
1.
*F. I -U, I 10/12/2002, Al" I -0 1 1 ...
RPS Cabinets 1558660 5/27/2001 4 .9 0 0 1 7 .3 9 3 1 9 .8 9 9
","'" I -" -
AF" -* 174 * *74 4 879 7 392 I 9 889 9, 46 Transmitterreplaced AF: 124 1 2374 4879 7 16.46 -0.17% -0.19% -0.16% -0.04% -0.05% 12/12/1999 AL:I -0.107 1 2.393 1 4.895 7.396 1 9! 2 89229Z w, dunngWO# 1525050 - 1525090 l',J 11/411999 AF:I -0.089 2.458 1 4.948 7.438 i 9.957 :5) PM. +..........~-4 All .0081
- -- +I -2408-- II-4 4912 -- ~4fl9 I~ 9914 13.40 -0.08% 0.52% 0.36% 0.27% 0.43%
9/22/1998 AI: -0 081
- 406 406 1 44912 912 !409 0 Z1 1514175 AL:l -0 (5) 9/19/1998 AF:I -0.126 1 2.373 1 4.881 1 7.387 I 9.901 AL: .0.088 1 2.400 1 4.892 F.388 I 9.886 5.12 -0,38% -0.27% -0.11% -0.01% 0.15%
1495204 4/16/1998 i __ 2.418
- i I4.909 9927 AF:l -0.107 7.432 I 1
-0101 1 241M 1 4 _ 1 AF:l IP/31A/0305/001 N 1740598 1709A 1 i 1 0 7 L: AF:
111/1912007 -0.085
-05g
-0085 J2.410 24150 2.410
[4.920!4 4 92022 J7.414 44 119.903 1 9. Enclosure 11.3.3 & - - -4~-- 18.27 0.24% 0.16% 0.30% 0.28% 0.17% 11.5.3 166248 5/1212006 .0.109 2.394 4.890 7.386 9.886 AF: .0.130 2.375 4.876 7.366 1 9.851 18.00 -0.30% -0.29% -0.34% -0.34% -0.41% 3RC PT0018P 1633338 11/10/2004 AL: -0.100 2.404 4.910 - 7.400 9.892 0 2nd Level RB AF: -0.066 2.440 4.946 7.436 i 9.921 17.58 0.38% 0.42% 0.46% 0.42% 0.33% cj~ 5/25/2003 AL: -0.104 2.398 4.900 7.394 1 9.888 1601293 -AF: .0.120 2.363 4.878 7.359 9.83 3RPSAFB20310 18.20 -0.11% -0.31% -0.03% -0.27% -0.13% "0 RPS Cabinets 1565643 11/17/2001-87!01AL -0.109 2.394 4.881 7.386 1 9.876
-49 AF: -0.112 2.382 4.912 7.390 9.890 18.86 -0.01% -0.09% 0.22% 0.03% 0.12%
AL: -0,111 2.391 4.890 7.387 I 7.41 9.878 9.923 1135187 4/2222000 AP: z
-0.088 12.421 14C9204.92 17.4181I 9.923
.... A~L
- 4. --
-0.1191
-- 4 1 2.391
~ ~ 4 891 7 391 I 9 887 17.71 0.31% 0.30% 0.29% 0.27% 0.36%
(8< 1503592 119 11 2 ' 7 34' 1 1 9897 10/31119... 1 -0 AF: AL:i -0.102 2.400 1 4.903 7.3901 19.573 00
Work Order Calibration Raw AFAL Data (2) Callbrail AFAL Drift Values m Number Datemt -0.111 V 2.389 V 4.889 V 7.389 V 9.889 V Interval(3) 1700psig 1900 psig 2100 psig 2300 psig 2500 pslg IP/1/N0305/001 0 Enclosure 11.2.1 & 1766640 1754* " " 4/1712008 AI IAF: -0.129 1 2.393 2.393 4.891 4.891 J 7.382 I 7.382 '1 9.881 9.881 13.80 -0.29% .0.07% -0.09% -0.19% .0.17% (5) 1t.4.1 2/122/2007 AL: 0.100 2.400 4.900 7.401 9.898 1670201 4 4 4 4.-4-t ___ _ 2/16/2007 AF: 0.006 .2.510 .4.984, 7.490 1 9.979 0.83% 1.07% 0.94% 0.79% 0.80% 2.30 1RC PT0019P 12/8/2006 AL 0.077 2403 4M0 7.41.1 1 9:899 1670438 (5) 2nd Level RB 1017/2006 AF 0.119 2.387 4.888 7.365 1 9.875 16.89 -0.15% -0.13% -0.19% -0.44% -.0.14% 1843664 5/11/2005 AL 0.104 2.400 4.907 7.409 9.889 4 4-4-4-4-4---.) - 1RPSAFC20310 4/9/2005 AF 0.129 2.420 4.865 7.378 1 9910 15.87 -0.40% 0,48% -0.12o% .0.04% 0.13% (s) AL: 0089 22.300 4:877 7.382 9!897 RPS Cabinets 1611170 12/13/2003 9202003 AF I 169 4:821 7.270 11 9.870 (5) PM for 16.82 -0.74% -1.11% .1.00% -1.48% -0.48% 4/26/2002 AL: -095 2.411 4.2 .7.418 9.918 4 4-+ 4 4. 4... WO#1610277 1578811 is with _________ 3/23/2002 AF 0.103 2.392 4.890 7.380 9.877 14.42 -0.07% -0.23% -0.20% -0.40% -0.46% (5) AV# 1611170. 1543962 1/8/2001 AL: .098 2.415 4.910 7.420 1 9.923 4 ,441t4 4 -
/1123/200AF 0.163 2.335 4.833 7330 1 9:822 10.71 -0.99% -0.95% -0.85% -0.71% -0.90% (s) 1544109 2/172000 0064 2.430 4.918 7.401 1 9912 1419121/00AP 008 2430 4.918 7.401 1 9.912
_094 2_ 7.49 0.20% 0.12% -0.10% -0.13% 0.11% 15165824 71411999 FAll .ln e4 41AR 4 9I9R 7414 ;I 9901 ALI -0084 2418 928 77 IAg: .I SR -, A~1~ A. O"4" .423 i I 9.916 C'D 91 AFj 0066 2435 4 CD -j IP/2!A/03051001 0 1679917 5/18/2007 AL:l -0.088 2.402 4.887 7. 9 ,
-i Enclosure 11.2.2 & AF:1 -0.088 2.402 4.887 7.386 9.882 0.20% 0.12% -0.03% -0.07% -0.08%
18.33 Co 11.4.2 1652930 11/8/200 "AL -0.1 2.390 4.890 7,393 I 9.890 CD A32 _! 7.433 9.939 1-11 17.87 0.02% 0.47% 0.43% 0.48% 0.49% 2RC PT0019P 5/11/2004 AL -0.112 2.386 4.889 7. 9.890 , - 4 44 0, 1623408 2nd Level RB ____________AF: -0.057 2.428 4.928 7.409 I 9.906 0.45% 0.43% 0.48% 0.39% 0.46% 1590530 18.07 15030111/8/2002 1/8202 -L 0 -0.102 2.385 4,880 7.3701 7.370 IT1 .6 9.860 A:
-0102 2.385 4.880 7.370
.-P 2RPSAFC20310 RPS Cabinets 1556661 SAF 512001 -009 2.389 4.895 7.396 I 1 18.271 -0.06% -0.04% -0.15% -0.26% -0.30% t~J 4 44 4 I_______ AF: -0.096 2.389 4.895 7.398 1 9.890 17.05 0.04% -0.09% 0.05% 0.01% -0.95% Transmitterreplaced 11/29/1999 AL: 1 2398 4.890 7.395 I 9.985 during WO# 1525091 1525091 11/12/1999 9 4.994 7.5051 10.008 t9ý, PM. AL: -0.100 2.404 4.900 7.409 I 9.909
'19.15 1 0.85% 1 1.05% 1 0.94% 1 0.96% 1 0.99%
1495205 4/8/1998 AF:I 0.019 2.521 5.023 7.504I 10.001 IP/3/A/0305/001 0 AL: -0.121 2.390 4.890 7.3901 9.889 1740582 111/19/2007 Enclosure 11,2.3 & AF:I -0.121 2.390 4.890 7.3901 1 9.889 4 4--4 -..-. 4 -.. 4 4-~---~ 4 18.27 -0.03% 0.05% 0.00% 0.09% 0.04% 11.4.3 All .. O11R 9R5 4 Attn 7 IR1 11RAS 1662469 5/12/2006 AL:l -0118 2385 4890 9 RR-S AF: .0.110 2.390 4.889 7.3891 9.889 18.00 -0.03% -0.10% -0.04% 0.04% 0.14% 3RC PT0019P 1633337 11/10/2004 Tp].!2 -0.107 2.400 4 4893 7AL: 7.3859 9.875
! 0Ci23 2nd Level RB __AF: -0.113!2.406 54924 7.40719.903 17.58 -0.05% 0.13% 0.21% 0,18% 0.15%
1601294 5/25/2003AL: -0.108 2.393 73891 9.888 .,..3 3RPSAFC20310 16014 55 3AF: -0.103 2.413 41920 74031 9.913 18.20 0.02% 0.09% 0.10% 0.02% 0.18% RPS Cabinets AL: -0.105 2.404 4.910 1. 7.4011 1 9.895 1565644 11/17/2001 -*- 4 - AFI -0.138 2.380 4872 7.379 9.865 18.96 -0.32% AFA -0135 2380 46 -0.26% -0.18% -0.32% -0.22% All' .t71119 9 398 4 9114 7 4t11 I 9 897 1530188 4/19/2000 AL: 1 -0112 398 49G4 7 AF: -0.090 2.428 4.931 7.4361 1 9.935 17.61 0.18% 0.24% 0.24% 0.25% 0.31% 4 4-4 1..... 4 AIl -0.108 2.404 7.4111 98904 1503593 1013111994 .... ..... .4 ... AF: -0.102 2.400 -r 7-801 9.8801
Work Order Calibration Raw AFAL Data Calbra ion AFAL Drift Values Number Date () -0. 111 V 2.389 V 4.889 V 7.389 V 9.889 V Inter~al(3) 1700psig 1900psig 2100psig 2300psig 2500psig IP/I/A/0305/001 P A ll. . ..... .... 6..7.
. ... 7. 376!
... 8R83 1767936 4/1612008 -01 UB 11 22.442 "
Enclosure 11.2.1 & ALI AF: -0.004 1 4.934 7.435;. 9.942 18.20 I 1.00% 0.60% 0.62% 0.47% 0.59% 11.4.1 2.382 4.872 7.388 11 9.883 1670439 10/10/2006 TAL: -0104 1RC PT0020P _____F: 0.40 . 2.350 4.833 7.3301 19.836 17.58 j .0.40% -0.51% -0.59% -0.62% -0.56% 1643665 4/23/2005 AL: -0.100 2.401 4.892 7.3921 1 9.892-2nd Level RB _____ _____AF: -0.160 2.286 4.729 7.1601 9.638 (6) 18.20 -0.54% -1.02% -1.54% -2.20% -2.53% 1128 10/17/2003 AL: -0.106 2.388 4.883 7.3801 9.891 ~1. 1 RPSAFD20310 _607 10/12/2003 AF: -0.071 2.462 4.933 7.426', 9.921 18.17 0.32% 0.63% 0.40% 0.38% 0.39% RPS Cabinets AL:. -0.103 2.399 4.893 7.3881 9.882 1578812 4/7/2002 I ____ _____AF: -0.085 -T2.417 4.903 7.4111 9.893 Transmitterreplaced 16.20 0.21% 0.12% 0.13% 0.04% 0.04% during WO# 1610278 1543963 11/30/2000 L -0.106 2.405 4.890 7.4071 9.889 AF: -0.180 12.320 4.624 7.3341 9.812 PM. AL:. -0.108 1 2.386 1 4.886 7.380! 9.882 17.94 I -0.72% -0.66% -0.62% -0.46% -0.70% 1515825 6/3/1999 AF:l -0.108 1 2.386 1 4.886 7.380: - 9.882 C43 IP/2/A0305/001 P AL: -0.088 1 2.408 1 4.915 7.3961 i 9.899 ( co" 1679918 5/18/2007 Enclosure 11.2.2 & AF:1 -0.088 2.408 1 4.915 7.3961 1 9.899 4 4.(. ---. 4 1>. 4 1114 18.33 0.13% 0.05% 0.12% 0.00% 0.19% qw-1 11.4.2 ALl .0 101 4 '403 I4 903 73961 I RRO 1652931 11/6/2005 ILJ -0101 2403 4903 AF: -0.101 1 2.403 1 4.903 7.396! 9.880 17.87 0.01% 0.04% 0.64% 0.06% -0.04% 02 2RC PT0020P 1623409 5/111/2004 AL: -0.102 12.399 14.899 7.390! 9.884 > .t 0 AL: . 0....10
... 4 .9 4 . .9 4
>111 816
- I 2nd Level RB AFI .0061 1 4S1 4 942 7 428: I 0o AF:l -0. 7474 1 2 18.07 0.41% 0.56% 0.49% 0.39% 0.42%
AL: -0.102 1 2.395 1 4.893 7.3W 1 9!812' 42 ýjj 1590531 11/8/2002 t,, 2RPSAFD20310 AF:I -0.102 1 2.395 4.893 7.390 I 9.874 4'- 171 i4 4. jIL 4 - 18.07 -0.06% -0.08% -0.08% -0.08% -0.23% RPS Cabinets All -0 096 I 2 403 I 4 901 7 398) 8897 9 > 1556663 5/7/2001 AL: 1 -0096 1 2403 1 4901 897 AF: -0,096 1 2.403 1 4.901 7.3981 1 9.897 17.67 0.24% 0.26% 0.16% 0.21% 0.31% 9.866 1525092 9.866 19.28 -0.31% -0.34% -0.22% -0.19% -0.28% 4- jj.~j. a I 9.894 1495206 10041
.4. £ IP/3/A/03051001 P 1740601 11/23/2007
/11 ALI 1tl*Dn7 F: -0.101
-005 1 145 2 2.400 29 490 4 go 7.401-g, 7.4759 9.918 9.960 Enclosure 11.2.3 & 18.20 I 0.58% 0.54% 0.70% 0.74% -0.24%
11.4.3 5/14/2006 AL -0108 2396 4.890 7.401 9 1662470 I 5/12/2006 AF 0127 2622 7.575 10.048 3RC PT0020P 1633338 1633338__ 11162004 _________4 -L AF: 0.100 2.407 2.601 5.082 4.900 5.100 7.398. 7.6001 9.894 10.090 17.81 f 2.31% I1 2.15% 1.82% 1.77% 1.54%
"i (7) 2nd Level RB (7) 17.71 2.10% 1.99% 2.13% 2.10% 1.86%
1601295 5/27/2003 5/23/2003 AL: AF:
-0.110 0.006 2.402 2.546 4.887 5.054 7.390!
7.560! 9.904 10.052 0 IRPSAFD20310 RPS Cabinets 1565645 11/17/2001 A A: .0.0509 2.462 4.918! 7.490! 9.998 I 18.13 1.04% 1.29% 1.36% 1.30% 1.42%
ý0i Transmnitters replaced 1535189I4/22 AL: -0.101 0 2.400 4.908 7.421 9.20 '.0 1535189 18.86 0.51% 0.62% 0.54% 069% 0.78%
during WOO 1633338 4/22/2000 -0038 2467 4980 745 t'Jo PM and WO# 1662470 t 4~4. ~ 9 - .~ - -, I 17.77 0.46% 0.64% 0.64% 0.49% 0.72% AL:I -0.084 1 2.403 I 4.916 7.410: , PM. 1503594 1012911998 7 09
*PT U ULL
- 41* I * *1*
1 4 --- l 1 9 Q81 CO*
OSC-9771, Rev. 0 Page 23 Table Notes for Table 7.2-2: Notes: 1) Date the calibration was performed.
- 2) The calibration points are in Volts DC (full scale output of buffer amplifier is 0 to 10 VDC). The calibration points are equivalent to 1700 psig, 1900 psig, 2100 psig, 2300 psig and 2500 psig. See Reference 5.C.
- 3) Calibration interval = (As-Found Date - As-Left Date)/30.44.
See Design Input 6.2.2.
- 4) The calibration points and AFAL drift values are in "% of Span".
Span = 10 Volts (Reference 5.C). AFAL drift values = (AFn - AIL_,)/span x 100%. See Section 3.0.
- 5) AFAL data for LTOP related transmitters were not included in the results in Tables 7.2-1 and 7.2-3. See Section 1.4, 7.2.1 and Assumption 6.1.2. The AFAL data for LTOP related transmitters was used to determine the initial statistics in Table 7.2-2.
6)-Th---A-FA--da-t-f6F-r-I--C-PT0020P at--he-2l-00--p-sig-,2300 p-slg ad 2500 psig calibration points were determined to be statistical outliers and not included in the final statistics in Table 7.2-3. See Section 7.2.1.
- 7) The AFAL data from 11/16/2004 to 5/12/2006 was determined to be from failing instruments and was not included in the final statistics in Table 7.2-3. See Section 7.2.1.
OSC-9771, Rev. 0 Page 24 7.3 Normality Tests/Bias Evaluation/Tolerance Intervals 7.3.1 Transmitter Normality Test Reference 5.G recommends that the D-Prime Test for normality be used for sample sizes greater than 50. The basics of the D-Prime Test are described below. The details of the D-Prime Test are described in References 5.G and 5.H. The D-Prime Test requires that the data be arranged into an ordered set (i, X1 ). Where: i = index number from 1 to n and Xi = the sampled data ordered from lowest to highest value. The ordered sets are shown in Tables 7.3-1 through 7.3-
- 3. An intermediate test statistic (Ti) is calculated for each data point as follows:
T={ i-(n+ 1)/2 }X i. The intermediate terms (Ti) are summed to determine the test statistic (T). The test statistic is divided by the sum of squares about the mean (S), which is equal to: S2 = (n- 1)* G2. Where: a = standard deviation of the tested sample from Table 7.2-1. The resultant D-Prime is equal to: D'= T/S. The resultant D-Prime is compared to the limits 'in Table 4-4 of Reference 5.G, to determine if the test refutes the assumption of normality (at 5% significance). If the resultant D-Prime is within the required range, the assumption of normality is established at the required significance. The results for the D-Prime Tests are also shown in Tables 7.3-1 through 7.3-3. The D-Prime Test for the 1700 psig calibration point will be shown below in detail as an example. All other D-Prime Tests are performed in the same way. The number of data points and standard deviation of the test sample (at the 1700 psig calibration point) are 52 and 0.392% span, respectively. See Table 7.2-3. Therefore: S' = (52 - 1) * (0.00392)2 S= 7.837 x 10-4 And S = (7.837 x 10-4)1/2
= 0.0280
'1 OSC-9771, Rev. 0 Page 25 The sum of the Ti values from Table 7.3-1 is 2.87; therefore, the resultant D-Prime is:
D' = T/S
= 2.87 - 0.0280
= 102.5 From Table 4-4 of Reference 5.G, linearly interpolated for a sample size of 52, a calculated D-Prime between 101.7 and 107.7 does not refute the assumption of normality (at 5% significance). Since the calculated D-Prime (= 102.5) is within the required range, the assumption of normality is established at the required significance.
A review of all the D-Prime Test results in Tables 7.3-1 through 7.3-3 shows that normality has been established at the required significance for all calibration points. Therefore, the distribution for AFAL drift data for the RPS RC Pressure transmitters is considered normal.
OSC-9771, Rev. 0 Page 26 Table 7.3-1 D-Prime Test Data For 1700 and 1900 psig Calibration Points D-prime Test D-p rime Test (for17 psig) (for 90 psig) Ti N= 52 Ti 0T5 1 0.255 N= 52
-0.75% 0.188 -1.02%
2 -0.72% 0.173 2 -0.66% 0.158 0.158 Sum of Ti = 2.87 Sum of T1= 3.27 3 -0.54% 0.124 3 -0.63% 0.145 4 -0.40% 0.088 Variance ofM = 1.54E-05 4 -0.51% 0.112 0.086
-0.41% Variance of) Q= 1.91E-05 5 -0.38% 0.080 5 0.086
-0.34% 0.068 6 -0.31% 0.062 S= 0.0280 6 -0.31% 0.068S = 0.0312 7 -0.30% 0.057 7 -0.29% 0.059 8 -0.26% 0.047 8 0.052
-0.25%
9 -0.200/, 0.034 9 -0.22% 0.043 10 -0.13% 0.021 10 0.035 11 12
-0.11%
-0.10%
0.017 0.014 I I D'= 102.5 11 12
-0.18%
-0.18%
-0.10%
0.027 0.025 I I [= 104.8 13 -0.07% 0.009 Normality = 101.7 to 107.7 13 -0.10% 0.013 Normality = 101.7 to 107.7 14 -0.07% 0.008 14 -0.09% 0.012 15 -0.07% 0.008 15 -0.09% 0.010 16 -0.06% 0.006 16 0.009 17 -0.06% 0.005 17 -0.08% 0.007 18 -0.06% 0.005 18 -0.04% 0.003 19 -0.05% 0.004 19 -0.02% 0.001 20 -0.03% 0.002 20 -0.02% 0.001 0.02% 21 -0.03% 0.002 21 0.03% -0.001 22 -0.02% 0.001 22 0.04% -0.001 23 -0.01% 0.000 23 -'0:04% -0.001 -0:01%-- -0:000 -04001 25 0.02% 0.000 25 0.05% -0.001 26 0.02% 0.000 26 0.05% 0.000 27 0.03% 0.000 27 0.08% 0.001 28 0.04% 0.001 28 0.09%/, 0.002 29 0.10% 0.003 29 0.12% 0.004 30 0.11% 0.004 30 0.12% 0.005 31 0.12% 0.006 31 0.13% 0.007 32 0.13% 0.008 32 0.16% 0.010 33 0.13% 0.009 33 0.24% 0.017 34 0.18% 0.014 34 0.25% 0.020 35 0.18% 0.016 35 0.26% 0.023 36 0.20% 0.020 36 0.26% 0.026 37 0.21% 0.023 37 0.30% 0.033 38 0.24% 0.029 38 0. 30%/ 0.036 39 0.24% 0.031 39 0.42% 0.055 40 0.31% 0.043 40 0.43% 0.060 41 0.32% 0.048 41 0.47r/6 0.071 42 0.38% 0.061 42 0.490/6 0.078 43 0.41% 0.070 43 0.54% 0.092 44 0.45% 0.081 44 0.56% 0.101 45 0.46% 0.087 45 0.60%/s 0.114 46 0.51% 0.102 46 0.62%/c 0.124 47 0.58% 0.122 47 0.63% 0.132 48 0.84% 0.185 48 0.64% 0.141 49 0.85% 0.196 49 0.84% 0.193 50 1.00% 0.240 50 0.87% 0.209 51 1.00% 0.250 51 1.05% 0.263 52 1.04% 0.270 52 1.29% 0.335
OSC-9771, Rev. 0 Page 27 Table 7.3-2 D-Prime Test Data For 2100 and 2300 psip Calibration Points D-prime Test D-prir nhe Test (for 21 psig) (for 23 0 psig) Ai T, A-. Tn N= 51 F N= 51
-0.73% 0.183 -0.70% 0.175 2 -0.62% 0.149 2 -0.62% 0*-149 of 'n = 2.97 Sum of Ti = 2.90 3 -0.61% 0.140 3 -0.57% 0.131 4 -0.59% 0.130 Vadanc eof)G= 1.73E-05 4 -0.46% 0.101 Vadance of) G= 1.70E-05 5 -0.34% 0.071 5 -0.34% 0.071 6 -0.32% 0.064 6 -0.27% 0.054 S = 0.0294 S= 0.0292 7 -0.31% 0.059 7 -0.26% 0.049 8 -0.22% 0.040 8 -0.22% 0.040 9 -0.19% 0.032 9 -0.19% 0.032 10 -0.15% 0.024 10 -0.18% 0.029 11 -0.11% 0-017 11 -0.14% 0.021 D0= 101.0 Dy= 99.3 12 -0.08% 0.011 12 -0.14% 0.020 13 -0.04% 0.005 Normality = 98.7 to 104.5 13 -0.08% 0.010 Normality = 98.7 to 104.5 14 -0.04% 0.005 14 -0.07"/, 0.008 15 -0.03% 0.003 15 -0.07% 0.008 16 -0.03% 0.003 16 -0.04% 0.004 17 -0.03% 0.003 17 -0.01% 0.001 18 -0.03% 0.002 18 -0.01% 0.001 19 0.00% 0.000 19 -0.01% 0.001 20 0.04% -0.002 20 0.00% 0.000 21 0.05% "-0.003 21 0.01% -0.001 22 0.10% -0.004 22 0.01% 0.000 23 0.11% -0.003 23 0.02% -0.001 -0.0021- --. 040%-
25 0.12% -0.001 25 0.04% 0.000 26 0.13% 0.000 26 0.04% 0.000 27 0.13% 0.001 27 0.06% 0.001 28 0.14% 0.003 28 0.06% 0.001 29 0.16% 0.005 29 .0.09% 0.003 30 0.19% 0,008 30 0.18% 0.007 31 0.21% 0.011 31 0.21% 0.011 32 0.22% 0.013 32 0.25% 0.015 33 0.24% 0.017 33 0.27% 0.019 34 0.29% 0.023 34 0.28% 0.022 35 0.29% 0.026 35 0.31% 0.028 36 0.30% 0.030 36 0.37% 0.037 37 0.40% 0.044 37 0.37% 0.041 38 - 0.43% 0.052 38 0.38% 0.046 39 0.46% 0.060 39 0.39% 0.051 40 0.48% 0.067 40 0.39% 0.055 41 0.49% 0.074 41 0.41% 0.062 42 0.54% 0.086 42 0.42% 0.067 43 0.60% 0.102 43 0.47% 0.080 44 0.62% 0.112 44 0.48% 0.086 45 0.64% 0.122 45 0.49% 0.093 46 0.66%. 0.132 46 0.60% 0.120 47 0.70% 0.147 47 0.69% 0.145 48 0.73% 0.161 48 0.74% 0.163 49 0.80% 0.184 49 0.96% 0.221 50 0.94% 0.226 50 1.23% 0.295 51 1.36% 0.340 51 1.30% 0.325
OSC-9771, Rev. 0 Page 28 Table 7.3-3 0 D-Prime Test Data For 2500 Dsig Calibration Points D-prime Test (for 2500 psig) TI TI N=51 1 -0.95% 0.238 I t..-.-.. -- 2 -0.84% 0.202 Sum of Ti = 3.21 3 -0.70% 0.161 _________ 4 -0.56% 0.123 Variance of A = 2.07E-05 5 -0.55% 0.116 I _ _ 6 -0.41% 0.082 0.02 7 -0.32% 0.061 F S= _ 0.0322 8 -0.30% 0.054 9 -0.28% 0.048 10 -0.24% 0.038I 11 -0.23% 0.035 U 99,7 12 -0.22% 0.031 13 -0.13% 0.017 Normality 98.7 to 104.5 14 -0.13% 0.016 15 -0.11% 0.012 16 -0.08% 0.008 17 -0.04% 0.004 18 -0.02% 0.002 19 0.00% 0.000 20 0.01% -0.001 21 0.02% -0.001 22 0.04% -0.002 23 0.04% -0.001 I IJ, U.UU-/O I-U 25 0.10% -0.001 26 0.11% 0.001 27 0.12% 0.000 28 0.13% 0.003 29 0.14% 0.004 30 0.15% 0.006 31 0.17% 0.009 32 0.18% 0.011 33 0.19% 0.013 34 0.25% 0.020 35 0.31% 0.028 36 0.31% 0.031 37 0.32% 0.035 38 ,0.33% 0.040 39 0.36% 0.047 40 0.390/6 0.055 41 0.42% 0.063 42 0.42% 0.067 43 0.45% 0.077 44 0.46% 0.083
- 45. 0.49% .0.093 46 0.59% 0.118 47 0.72% 0.151 48 0.78% 0.172 49 0.99% 0.228 50 1.06% 0.254 51 1.42% 0.355
OSC-9771, Rev. 0 Page 29 7.3.2 Bias Evaluation The bias evaluation is based on determining a confidence interval for the mean. The evaluation is described in detail in Reference 5.G. In short, if the confidence interval includes zero, then there is no reason to reject the assumption that the mean is zero (i.e., no bias) at the stated confidence level. Per Table 7.2-3, the standard deviations are all > 0.25% span and the sample size is < 60; therefore, the maximum value of a non-biased mean from Table 4.5 of Reference 5.G is +/- 0.065% span. Per Table 7.2-3, the means at all the calibration points are > +/- 0.065% span and thus should be treated as a bias. The greatest mean is + 0.161% span at the 2100 psig calibration point. This value will be applied in both directions to determine a bias that is bounding for all calibration points. Thus, the bias for the RPS RC Pressure transmitter Analyzed Drift determination is +/- 0.161% span or +/- 1.3 psi (= + 0. 161%/o00% x 800 psi). 7.3.3 Tolerance Interval Per Section 3.0 and Reference 5.G, the tolerance interval (TI) is calculated as follows: TI = *t +/- (TIF 9 5/95 x Table 7.3-4 shows the Tolerance Intervals for all calibration points. Table 7.3-4 is based on the final statistics in Table 7.2-3 and the Tolerance Interval Factors from Table 4.2 of Reference 5.G. From Table 4.2 of Reference 5.G, using linear interpolation, the 95/95 Tolerance Interval Factor (TIF95 /95 ) is 2.37 for n = 52 and 2.38 for n = 51. Table 7.3-4 RPC RC Pressure Transmitter Tolerance Intervals Statistic 1700 psig 1900 psig 2100 psig 2300 psig 2500 psig Number of Points 52 52 51 51 51 Mean +0.103% +0.124% +0.161% +0.141% +0.106% Standard Deviation 0.392% 0.437% 0.416% 0.412% 0.455% Tolerance Factor 2.37 2.37 2.38 2.38 2.38 Upper Tolerance Interval = +1.03% +1.16% +1.15% +1.12% +1.19% Lower Tolerance Interval = -0.83% -0.91% -0.83% -0.84% -0.98%
OSC-9771, Rev. 0 Page 30 It can be seen in Table 7.3-4 that a tolerance interval of + 1.19% span to - 0.98% span for the RPS RC Pressure Transmitters is bounding at all calibration points. Per Section 3.0 and Reference 5.G, the random portion of the 18 month Analyzed Drift is: ADRANDOM = (TIF 95195 x a x NAF). Where NAF is the Normality Adjustment Factor applied to non-normal sample distributions. Section 7.3.1 shows that the RPS RC Pressure Transmitter AFAL drift data is normally distributed; therefore, NAF = 1. From Table 7.3-4, the bounding TIF 95/95 is 2.38 and the bounding standard deviation is 0.455% span. Therefore, the random portion of the 18 month Analyzed Drift is: ADRANDOM = - (2.38 x 0.455% x 1.0),
= 1.08% span.
This is equivalent to +/- 8.6 psig ( + 1.08% span/I 00% x 800 psig). From Section 7.3.2, the bias portion of the 18 month Analyzed Drift is +/- 1.3 psig. Therefore, the 18 month Analyzed Drift for the RPS RC Pressure Transmitters is +/- 1.3 psia (bias) +/- 8.6 psig (random). S7.4 Drift Data Time Dependency The determination of time dependency from multi-cycle data is discussed in detail in Reference 5.G. In short, the drift data from the first and second cycle are added to determine the first set of multi-cycle data. Then the third and the fourth cycles are added, etc. This is continued until as much multi-cycle data that can be obtained has been obtained. Note, that there is no overlap of cycles and no account is taken as to whether or not the instruments were reset. Note also that the multi-cycle data is not being used to determine a time dependent uncertainty; there is insufficientdata to determine the magnitude of the time dependence. The multi-cycle data is only being used to support the assumption of moderate time dependency (Assumption 6.1.1). For further details see Section 3.0 and Reference 5.G. 7.4.1 Transmitter Time Dependency The RPS RC Pressure Transmitter multi-cycle data is shown in Table 7.4-2. Note that this data only includes the AFAL drift data for the non-LTOP related transmitters. The comparison of the multi-cycle data and the single cycle data is shown in Table 7.4-1.
OSC-9771, Rev. 0 Page 31 Table 7.4-1 Non-LTOP Transmitter Comparison CombinedData Statistic (1) Multi-Cycle (2) Single Cycle (3) Number of Data Points 122 257 Data Average 0.186% 0.127% Data Standard Deviation 0.435% 0.420% Average Calibration Interval 36.0 18.0 Notes 1) As determined by Microsoft Excel's COUNT, STDEV and AVERAGE functions.
- 2) Based on all the recorded multi-cycle data in Table 7.4-2.
- 3) Based on all the recorded single cycle data in Table 7.2-4.
By inspection of the means in Table 7.4-1, the multi-cycle data average shows a small increase over the single cycle data average. For conservatism, a strong time dependency will be applied to the bias portion of the RPS RC Pressure Transmitter Analyzed Drift. Per Section 3.0 and Reference 5.G, for a strong time dependency, th~--l~i5p-o-fr-f--of-t e-extei-d-d cycl-Aiin--alyz-ed-Dr-iff-(-A-D-E BI-As-) is determined as follows: 0 ADE BIAS = ADBIAS x CIO C'o Where CIE = length of extended calibration interval and CIO = length of the original calibration interval. Per Table 7.4-1, the average calibration interval for the multi-cycle data and the single cycle data is 36.0 months and 18.0 months, respectively. Per Section 7.3.2, the 18 month Analyzed Drift bias term was determined to be +/- 1.3 psi. Therefore, the extended cycle Analyzed Drift bias term is: ADE BIAS +/- 1.3 psi x 36.0 mo 18.0 moo
= +/- 2.6 psi AD2 BIAS = (+ 2 6 psi)/800 psi x 100%,
0.33% span If there was a significant time dependency in the random portion of the analyzed drift, then this time dependency would cause the standard deviation of the multi-cycle data to expand relative to the standard deviation of the single cycle data. The time dependency would be manifested in the ratio of the multi-cycle standard deviations to the single cycle standard deviations.
OSC-9771, Rev. 0 Page 32 The ratio of the average calibration interval for the multi-cycle data to the average calibration interval for the single cycle data is 2.0 (= 36.0 months - 18.0 months). Per Reference 5.G, the maximum or critical ratio that supports moderate time dependency is 1.41 (= 2.01"2). The standard deviation for all the recorded multi-cycle data and all the recorded single cycle data in Table 7.2-1 are 0.435% span and 0.420% span, respectively. The ratio of the multi-cycle standard deviation to the single cycle standard deviation is 1.04 (= 0.435% - 0.420%). The ratio of the standard deviations is less than the critical value of 1.41. Therefore, the assumption of moderate time dependency is validated (Assumption 6.1.1). Per Section 3.0 and Reference 5.G, for moderate time dependency, the random portion of the extended cycle Analyzed Drift (ADE RANDOM) is determined as follows: ADE RANDOM - ADRANDOM f7.E 4* CIO Where: CIE is the extended cycle calibration interval and CIO is the average calibration time interval from the sample data. . From Section 7.3.3, the random portion of the 18 month Analyzed Drift is +/- 8.6 psi. Therefore:
- - (+/--8:6-psi)-x- .- ,
A-DE-RANDOM 0 =+/- 11.1 psi. ADE RANDOM = (+ 11.1 psi)/800 psi x I 00%,
= 1.39% span The overall extended cycle Analyzed Drift is the combination of the bias and random portions. Therefore, the RPS RC Pressure Transmitter overall extended cycle Analyzed Drift is +/- 2.6 psi (bias) +/- 11.1 psi (random).
Work Order Calibration AFAL Drift Values(2) C Multi-Cvcle AFAL Drift Values(4) Number Date(1) 1700 psig 1900 psig 2100 psig 2300 psig 2500 psig Interv.in3 1700 psig 1900psig 2100 psig 2300psig 2500 psig IPIllA/03051001 M 1767934 4/16/2008 Enclosure 11.3.1 & 0.03% 0.49% 0.60% 0.41% 0.42% 11.5.1 35.78 -0.35% 0.08% -0.13% -0.16% -0.13% 1670436 10/10/2006
-0.38% -0.41% -0.73% -0.57% -0.55%
1RC PTOO17P 1643662 4/23/2005 2nd Level RB -0.02% 0.14% -0.04% 0.05%
-0.06%
1610275 10/12/2003 36.53 0.94% 0.85% 0.87% 0.56% 0.50% 1RPSAFA20307 1.00% 0.87% 0.73% 0.60% 0.45% RPS Cabinets 1578809 41/72002
-0.20% 0.02% 0.11% 0.06% 0.10%
1543960 11130/2000 - 34.13 -0.33% 0.05% 0.08% -0.01% -0.01%
-0.13% 0.03% -0.03% -0.07% -0.11%
1515822 6/3/1999 C/) IP/2/A/0305/001 M cc, 1679915 5/18/2007 Enclosure 11.3.2 & -0.07% -0.22% -0.04% 0.01% -0.13% CD 11.5.2 -0.35% -0.17% -0.15% 1652928 11/6/2005 36.20 -0.14% -0.40%
-0.07% -0.18% -0.31% -0.18% -0.02% '0~
2RC PT0017P 2nd Level RB 1623406 5/11/2004 <Cs (A 0.11% 0.26% 0.19% 0.31% 0.25% 36.33 0.21% 0.34% 0.32% 0.30% 0.27% ~s 0 1590528 11/8/2002 2RPSAFA20307 RPS Cabinets 0.10% 0.08% 0.13% ý-0.01% 0.02% ws -ri 1556659 5/11/2001 0A Transmitterreplaced 0.18% -0.02% -0.03% -0.01% 0.11% dufing WO# 1525089 1525089 11/12/1999 36.70 102% 082% 077% 122% 117% PM. 0.84% 0.84% 0.80% 1.23% 1.06% I 1495203 4/10/1998
= I IP/1/A/0305/001 N 17935 4/16/2008 3,
Enclosure 11.3.1 & 1 0.13% 0.30% 0.66% 0.37% 0.32% 11.5.1 1670437 10/10/2006 - 35.78 -0.62% -0.33% 0.05% -0.33% -0.52%
-0.75% -0.63% -0.61% -0.70% -0.84%
1RC PT0018P 1643663 4/23/2005 2nd Level RB -0.10% -0.10% -0.11% -0.14% 0.01% 0 10/12/2003 : . , 36.53 0.02% 0.15% 0.18% 0.23% 0.14% 1RPSAFB20310 1610276 0.12% 0.25% 0.29% 0.37% 0.13% RPS Cabinets 1578810 4M/2002 Cs
-0.02% 0.04% 0.11% -0.01% 0.00%
1543961 11/30/2000 34.13 -0.09% -0.21% -0.08% -0.15% -0.22%
-0.07% -0.25% -0.19% -0.14% -0.22%
1515823 I 6/3/1999 ______________ A - A
0 Work Order Calibration AFAL Drift Values I Calibration Multi-Cycle AFAL Drift Values (4) Number Date () 1700 psig 1900 psig 2100 psig 2300pssig 2500osig lntervalia 1700 psig 1900psig 2100 psig 2300psig 2500 psig IP/3/A[03051001 N 1740598 11/1912007 Enclosure 11.3.3 & 0.24% 0.16% 0.30% 0.28% 0.17% 11.5.3 1662468 5/12/2006 36.27 -0.06% -0.13% -0.04% -0.06% -0.24%
-0.30% -0.29% -0.34% -0.34% -0.41%
3RC PT0018P 1633336 11/1012004 2nd Level RB 0.38% 0.42% 0.46% 0.42% 0.3 0.38 0.42% 0.46 0- % 35.78 1601293 5/25/2003 0.27% 0.11% 0.43% 0.15% 0.20% 3RPSAFB20310
-0.11% -0.31% -0.03% -0.27% -0.13%
RPS Cabinets 1565643 11/17/2001
-0.01% -0.09% 0.22% 0.03% 0.12%
1535187 4122/2000 36.56 0.30% 0.21% 0.51% 0.30% 0.48% 0.31% 0.30% 0.29% 0,27% 0.36% 1503592 10/31/1998 CD CD IP/2/A/0305/001 Q Enclosure 11.2.2 & 11.4.2 1679917 1652930 511812007 11/6/2005 0.20% 0.12% -0.03% 0.43%
-0.07%
0.48% I
-0.08%
00.49% 36.20 022% 0.59% 0.40% 0.41% 0.41% 0 2RC PT0019P 0.02% 0.47% >s-1623408 5/11/2004 0~ 2nd Level RB 0.45% 0.43% 0.48% 0.39% 0.46% 1590530 11/8/2002 36.33 0.39% 0.39% 0.33% 0.13% 0.16% 2RPSAFC20310 -0.06% -0.04% -0.15% -0.26% -0.30% RPS Cabinets 1556661 5/1/2001 Transnrtterreplaced 11/29/1999 0.04% -0.09% 0.05% 0.01% -0.95% during WO# 1525091 1525091 ' 36.76 0.89% 0.96% 0.99% 0.97% 0.04% 11/12/1999 PM. 0.850% 1.05% 0.94% 0.96% 0.99% 1495205 4/8/1998 IP/3/A10305/001 0 1740582 11/19/2007 Enclosure 11.2.3 & -0.03% 0.05% 0.00% 0.09% 0.04% 11.4.3 5/12/2006 36.27 -0.06% -0.05% -0.04% 0.13% 0.18% 1662469
-0.03% -0.10% -0.04% 0.04% 0.14%
3RC PTOO19P 2nd Level RB 1633337 11/10/2004 0
-0.05% 0.13% 0.21% 0.18% 0.15% Ci2 1601294 5/25/2003 I ' 35.78 -0.03% 0.22% 0.31% 0.20% 0.33%
3RPSAFC20310 0.02% 0.09% 0.10% 0.02% 0.18% RPS Cabinets 1565644 11/17/2001 UQCO
-0.26% -0.18% -0.32% -0.22% -0.32%
1530188 4/19/2000 36.56 -0.08% 0.06% -0.08% 0.03% -0.01% -OJ 0,18% 0.24% 0.24% 0.25% 0.31% 1503593 10/31/1998
0 WorkOrder Calibration AFAL Drift Values () Calibration Multi-Cycle AFAL Drift Values 4m Number Date(I) 1700 psig 1900 psig 2100psig 2300psig 2500psig Inel a 1700psig 1900psig 2100 psig 2300 psig 2500psig IPIl/N03051001 P 1767936 4/16/2008 -0.15% Enclosure 11.2.1 & 0.62% I0.47% 1.00% 0.60% 0.59% 11.4.1 0% 0% 0.62 . % 35.78 -0.15% 1670439 10/10/2006 35.78 0.60% 0.09% 0.03% 0.03%
-0.40% -0.51% -0.59% -0.62% -0.56%
1RC PT0020P 4/2312005 184M665 2nd Level RB 71/17/2003 -. 4% 1 -1.02% -1.54% -2.20% 2.53%5) 365 02 % -. 9 1RPSAFD20310 1610278 10/12/2003 J~ ~ ~ .0 RPS Cabinets 0.32% I 0.63% 040% 0.36% 0.39% I 1578812 4/712002 - . I Transmitter replaced 0.21% 0.12% 0,13% 0.04% 0.04% B dudng K4VOO 1610278 1543963 11/3012000 + 34.13 -0.51% -0.54% -0.49% -0.42% -0.66% PM. -0.72% -0.66% -0.62% -0.46% -0.70% 1518825 6/3/1999 ________ .1 1 .1 U,- IP/21A/03051001 P 1679918 5/18007 Enclosure 11.2.2 & -3 11.4.2 0.13% 0.05% 0.12% 0.00% 0.19% 1652931 11/6/2005 0 - 0.06% - 36.20 0.14% 0.09% 0.16% 0.06% 0.15% 0.01% 0.04% 0.04% 0.06% -i0.04% zCDo 2RC PT0020P 162409 5/11/2004 0 ob 2nd Level RB 0.41% 0.56% 0.49% 0.39% I0.42% 36.14 0.35% 0.48% 0.41% 0.31% 0.19%
~1.
2RPSAFD20310 1590531 11/8/2002 RPS Cabinets -006% -0.08% -0.08% -0.08% -0.23% -.4 0* 1556683 5/7/2001 0.24% 0.26% 0.16% 0.21% 0.31%
- r. 36,96 -0.07%
00%-.6 -0.08% 00%00%3.6 -0.06% 0.02%
.2 0.03%
1525092 11/16/1999 I 4"- I
-0.31% -0.34% -0.22% -0.19% -0.28%
1495206 4/8/1998 IP/3/A/0305/001 P 1740601 11/23/2007 0) Enclosure 11.2.3 & , . 11/19/2007 0.58% 0.54% 0.70% i 0.74% -0.24%(6)
-0.24%
11.4.3 1662470 5114/2006 1640 5/12/2006 2.31% 2.15% 1.82% 1.77% 1.54% 3RC PT0020P 1633338 11/16/2004 2nd Level RB 0 2.10% 1.99% 2.13% 2.10% 1.86% 18) 1601295 5/27/2003 1RPSAFD20310 5/23/2003 1.04% 1.29% 1.36% 1.30% 1.42% RPS Cabinets 1565645 11/17/2001 Transrrittef replaced 0.51% 0.62% 0.54% 0.69% 0.78% CD3 during KV# 163333s 1535189 4/22/2000 4 4 36.63 1 0.97% 1.26% 1.18% 1.18% I 1.50% w. PM and WO# 1662470 0.46% 0.64% 0.64% 0.49% 0.72% r*r PM. 1503594 10/29/1998 LA
OSC-9771, Rev. 0 Page 36 Table Notes for Table 7.4-2:
- Notes: 1) Date of the calibration was performed.
- 2) Single cycle AFAL drift values from Table 7.2-4.
- 3) Calibration interval = (As-Found Date - As-Left Date)/30.44. See Design Input 6.2.2. The multi-cycle interval pattern was to skip every other calibration date. See Reference 5.G for details.
- 4) The AFAL drift values are in "% of Span".
Multi-Cycle AFAL drift values = D,+2 + D,+1
= (AFn+3 - ALn+2) + (AF.+2 - ALn+l).
See Section 3.0 and Reference 5.G for further details on the methodology for determining two cycle data.
- 5) These multi-cycle data points include single cycle data points that were determined to be outliers. Therefore, they were not included in the multi-cycle data.
- 6) These multi-cycle data points incltude-singlk cyc-- -data--poin*-That were determined to be from failing instruments. Therefore, they were not included in the multi-cycle data.
OSC-9771, Rev. 0 Page 37 7.5 Acceptable Limit (AL) Determination and Drift Data Comparison 0 The Acceptable Limit (AL) is determined for the current instrument loop configuration and then compared to the raw AFAL drift data to fulfill the requirements of NRC GL 91-04 Issue 1. Per Section 3.0, instrument accuracy, drift and resolution (if used during calibration) should be included in determining an acceptable limit (AL) along with the loop M&TE equipment error. The Reactor Protection System RC Pressure bistable strings consist of a transmitter, buffer amplifier and bistable. However, only the Rosemount 1154 transmitter and the buffer amplifier are applicable here. See Sections 1.3 and 1.4, and Reference 5.C. All uncertainties given below were taken or derived from the RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Limit Calculation (Reference 5.A.a) unless otherwise stated. The upper range limit for a Rosemount Model 1154 GP9RB is 3000 psig and the span of the RPS RC Pressure loops is 800 psig. Transmitter Accuracy: ATR = +/- 0.25% span Transmitter Drift DTR = +/- 0.2% URL/30 month
= +/- 0.2% x (3000 psi/800 psi)
= +/- 0.75% span Buffer Amplifier Accuracy: AAF = +/-0.15% span Buffer Amplifier Drift: DAF = +/- 0.1% span/month (based on CFT -
45 days staggered basis = 180 days)
= +/- [180/30 x (0.1%)2]I/2
= + 0.25% span M&TE Pressure Error: MTE= +/- 0.86% span*
- From Section 7.3.5.1 of Reference 5.A.b. Reference 5.A.a does not include a pressure M&TE error.
The RPS RC Pressure Transmitter Acceptable Limit is: 2
=-[ATR + DTR + AAF2 + DAF2 + MTE 112 2 2 ALTR
_ -[0.252 +0.752 +0.152 ++/-0.252+0.862]I/2
+ 1.20% span.
OSC-9771, Rev. 0 Page 38 From Table 7.2-4, for non-LTOP related transmitters only (see Assumption 6.1.2), the 18 month Acceptable Limit (+/- 1.20% span) is exceeded by the AFAL drift data twice at the 1700 psig calibration point, three times at the 1900 psig calibration point and 4 times each at the 2100 psig and 2500 psig calibration points and 5 times at the 2300 psig calibration points. However, in most of these cases the occurrences were due to the failing transmitters. Specifically, the 3RC PT0020P transmitter was replaced twice for poor performance, once in 2004 and again in 2006. The data during this period is not considered representative of the typical loop performance and consequently was not included in the final statistics for the transmitter. In addition, the 2RC PT0017P transmitter was replaced for poor performance in 1999. See Table 7.2-4. The data, which was the basis for the replacement of the transmitters, will not be included in the overall evaluation Rosemount Model 11 54DP9RB transmitters with respect to Issue 1 of Enclosure 2 to NRC Generic Letter 91-04.* Thus, excluding the data from the failing transmitter, the maximum number of times the AFAL drift data exceeded the acceptable limit is 2 (at the 2300 psig calibration point) and this represents 4.2% of the total {= 2/(51 - 3) x 100%}. This is less than the limit of 5% given in Reference 5.G. Therefore, the RPS RC Pressure Transmitter calibration data meets the requirements of Issue 1 of Enclosure 2 to NRC Generic Letter 91-04.
- The definitive solution for instruments that are unable to perform for extended
__fuel cycles is to replace them with instruments that can. Although unrelatedto the cycle extension program, these specific Iransmitterswere refll-edfo6--this reason (i.e., they could not perform adequatelyfor the duration of the cycle). It is. true that these transmitters were replaced with like models; however, the principle is the same. Therefore, the question to be answered by Issue I of Generic Letter 91-04 is better phrased as to whether there is a systemic reason that the transmitters used in this application,which are Rosemount Model 1154DP, should not be used for an extended cycle. The Rosemount Model 1154 transmitter is a commonly used transmitterin the nuclear industry. They are operatingreliably at facilities that have already gone to 24 month fuel cycles. Thus, regardless of what is and isn't considereda failure with respect to Issue 1 of GL 91-04 in this analysis, the Rosemount 1154 transmitter has demonstrated acceptable performance for extendedfuel cycles. 7.6 Comparison of Analyzed Drift (ADE) with Uncertainty Calculation Limits and Plant Procedure Acceptance Criteria The Analyzed Drift for the extended cycle (ADE) is compared to the applicable instrument uncertainties for a 30 month calibration interval and the existing plant surveillance procedure acceptance criteria.
OSC-9771, Rev. 0 Page 39 7.6.1 Comparison of Analyzed Drift (ADE) with Uncertainty Calculation Limits From Section 7.5 above and based on Reference 5.A.a, the 18 month Acceptable Limit is +/- 1.20% span or +/- 9.6 psi (-+ 1.20% span/100% x 800 psig). A review of References 5.A.a shows that the drift terms support a maximum 30 month calibration interval; therefore, the 30 month Acceptable Limit is equal to the 18 month Acceptable Limit. From Section 7.4.1, the extended cycle Analyzed Drift is +/- 2.6 psi (bias) +/- 11.1 psi (random) = +/- 13.7 psi. The extended cycle Analyzed Drift is greater than-the 30 month Acceptable Limit that was determined for the existing loop configuration. Corrective Action #2 of PIP 0-09-4103 has been issued to evaluate the effects of the extended cycle Analyzed Drift on the RPS RC Pressure Total Loop Uncertainties (References 5.A.a). In addition, the instrument uncertainty calculation for the existing RPS RC Pressure instruments (Reference 5.A.a) should be revised to include pressure M&TE errors. Uncertainty Calculation OSC-8828 (Reference 5.A.b) documents the uncertainty of the RPS RC Pressure instrument strings based on the implementation of the Digital RPS/ESFAS replacement modifications (Reference 5.K). The pressure transmitters are the only component retained with the new design. The extended cycle Analyzed Drift determined in Section 7.4.1 of this analysis is for the transmitter/buffer amplifier combination. Thus, a direct comparison of Analyzed Drift to the instrument uncertainties for the new design is not possible. However, itis expec-ted atffthetransmitter isthedoinate contrib--utor to thAnalyzed Drift. Therefore, since the extended cycle Analyzed Drift for the existing design is greater than the 30 month Acceptable Limit, the transmitter is expected to be the dominate contributor to the Analyzed Drift and, the transmitter is being retained in the new design, the instrument uncertainties in Reference 5.A.b should be reviewed to take these considerations into account. Corrective Action #2 of PIP 0-09-4103 has also been issued to evaluate the effects of the extended cycle Analyzed Drift on the new Digital RPS RC Pressure Total Loop Uncertainties (Reference 5.A.b). Once installed, performance of the cabinet electronics associated with the Digital RPS/ESFAS will be monitored by the ONS calibration surveillance procedure review program as described in the Instrument Drift Analysis Methodology in Support of 24 Month Surveillance Interval (Reference 5.G). This monitoring will ensure the as-found calibration values for the new equipment do not exceed the acceptable limits as defined in Reference 5.A.b, except on rare occasions.
OSC-9771, Rev. 0 Page 40 7.6.2 Comparison of Analyzed Drift/Uncertainty Calculation Limits to 18-month Calibration Tolerances The current calibration procedure as-left/as-found setting tolerance for the RPS RC Pressure Transmitter/Buffer Amplifier combination is +/- 0.040 Vdc, which is
+/-3.2 psi (= +/-0.040 Vdc/10 Vdc x 800 psig, see Enclosure 11.3.1 of IP/0/A/0305/001 M, Reference 5.C). The setting tolerance used in the current uncertainty calculation (Reference 5.A.a) is the same as is used in the current calibration procedure (Reference 5.C). Per Section 7.4.1, the extended cycle Analyzed Drift (ADE) for the transmitter is +/- 2.6 psi (bias) +/- 11.1 psi (random)
= + 13.7 psi. The extended cycle AD is greater than the As-Found Calibration Tolerance; therefore, the extended cycle AD cannot be exceeded without the As-Found Calibration Tolerance also being exceeded.
Per Section 7.11.1 of Reference 5.A.b, the transmitter As-Found acceptance criteria for the future calibration procedures to be implemented when the Digital RPS/ESFAS is installed is +/- 9.6 psi (= +/- 1.194% span/I00% x 800 psig). Per Section 7.4.1, the extended cycle Analyzed Drift (ADE) for the transmitter is +/- 2.6 psi (bias) +/- 11.1 psi (random) = +/- 13.7 psi. The extended cycle AD is greater than the As-Found acceptance criteria; therefore, the extended cycle AD cannot be exceeded without the As-Found acceptance criteria also being exceeded. Both the current As-Found Calibration Tolerance and the future transmitter As-Found acceptance criteria will identify drift in excess of that accounted for by the extended cycle AD and; therefore, are adequate for the existing and planned Digital RPS/ESFAS transmitter arrangements. 7.6.3 Comparison of Analyzed Drift/Uncertainty Calculation Limits to the Channel Functional Test The Channel Functional Test surveillance procedure (Reference 5.J) tests only the Bailey cabinet components located in the Control Roomand does not include the field mounted Rosemount pressure transmitters. From Reference 5.J, the Channel Functional Test is performed using the Bailey Pressure Test Module which disconnects the Rosemount transmitter and injects a simulated transmitter (test) signal into the RPS/ESFAS channel. Using the test signal, the RPS/ESFAS channel buffer amplifier and bistable calibrations are verified using the same overlap testing methods and acceptance criteria (voltage values) as is used for the 18-month calibration procedures (Reference 5.C). The channel functional tests are performed every 92 days as required by Technical Specifications and are unaffected by transition to 24 month fuel cycles.
OSC-9771, Rev. 0 Page 41 As discussed in Section 1.1, the replacement AREVA digital RPS/ESFAS equipment will be certified for a 30-month calibration interval and will include revised Channel Calibration Tests as well as revised Channel Functional Tests and Channel Checks for the replacement AREVA digital RPS/ESFAS equipment. No calibrations or adjustments will be made as part of the channel functional test for the new equipment. 7.6.4 Comparison of Analyzed Drift/Uncertainty Calculation Limits to Channel Check Test The Plant Surveillance Procedure (Reference 5.D) places the following required condition on the RPS RC Pressure OAC Indication loops:
"Verify computer readouts agree within 26 psi."
References 5.M.a, 5.M.b and 5.M.c determined a proposed channel check limit of 23 psi for the RPS RC Pressure instrument strings after installation of the replacement Digital RPS/ESFAS system. Thus, the Channel Check Limit for the existing loop configuration is 26 psi and the proposed Channel Check Limit for the Digital RPS/ESFAS loop configuration is 23 psi. The OAC indication signal is currently obtained from an isolated analog output of
.1--1--Th-i--e-xte-n-de-d -cycl--eAly-z-ed-Dift is th--b-ffer-amplifi-er.- -ee Fi-gure 7--
based on the AFAL drift of the transmitter and buffer amplifier configuration. Therefore, it does not include the A/D portion of the OAC Indication loop. However, the contribution of drift of the A/D portion of the OAC Indication loop is expected to be small relative to the contribution of the transmitter. For the Digital RPS/ESFAS Upgrade, the signal will be transmitted via OPC using the OAC/OPC Gateway to the OAC (see Reference 5.A.b). Again; however, the contribution of drift of the A/D function of the new Digital RPS/ESFAS is expected to be small relative to the contribution of the transmitter. In either case, for the existing loop configuration or the planned Digital RPS/ESFAS loop
. configuration, the extended cycle Analyzed Drift term from Section 7.4.1 will serve as a reasonable proxy for their equivalent OAC Indication.
Channel checks are defined by the ONS Technical Specifications as "the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter." As these comparisons are performed during unit operation, expected uncertainties associated with normal unit operation are applicable in determining a channel check limit. These expected normal uncertainties are obtained from the associated instrument setpoint/uncertainty calculation considering the effect of the analyzed drift Amok determined in this analysis.
OSC-9771, Rev. 0 Page 42 Based on the above, a channel comparison uncertainty (CCU) will be determined including uncertainty terms for accuracy, drift, resolution, setting tolerances, M&TE, and moderate temperature effects for all instruments in the string used to verify the channel check. Inclusion of any additional terms shall be justified. The channel check limit is then determined by SRSS of the CCU values. It should be noted that other process or operational effects not accounted for in the determination of CCU (process dynamics due to physical connections, process noise, unit power level, etc.) may impact actual channel readings and warrant inclusion in the channel check limit. Per Section 7.6.1, the analyzed drift for 30 months is larger than the 30 month Acceptable Limit for the current OAC Indication; therefore, ADE will be used in the determination of CCU. From Section 7.4.1, ADE = +/- 0.33% span (bias) +/- 1.39% span (random). Only the temperature effect and setting tolerance terms have not been accounted for in the Acceptable Limit/ADE comparisons in Sections 7.5 and 7.6.1. Half of the worst case normal temperature effect is deemed appropriate for use in the comparison uncertainty. From Reference 5.A.a, for the existing loop configuration, the temperature effect is +/- 1.66% span and the OAC Indication setting tolerance is +/- 0.40% span. The Acceptable Limit is taken from Section 7.5 (and shown applicable to a 30 month calibration interval in Section 7.6.1). The existing loop configuration CCU is: CCU = +/- 0.33% +/- [1.392 + (1.66/2)2 + 0.42]"'
= + 0.33% span (bias) +/- 1.67% span (random).
CCU +/- {0.33% span +/- 1.67% span}/100% x 800 psig
= + 2.6 psi (bias) +/- 13.4 psi (random).
Based the extended cycle instrument uncertainties for the current loop configuration, the comparison of two OAC indication channels should be within 22 psi {1 2.6 psi + [2 x (13.4 psi) 2]12 }. The current channel check limit of 26 psi is greater than that based extended cycle instrument uncertainties and; therefore, may be too permissive for the current loop configuration. The proposed channel check limit for the RPS RC Pressure instrument strings after installation of the replacement Digital RPS/ESFAS system is 23 psi (References 5.M.a, 5.M.b and 5.M~c). The proposed channel check limit- is based on the uncertainties in Reference 5.A.b during normal operating conditions. Corrective Action #2 of PIP 0 4103 is to evaluate the effects of the extended cycle Analyzed Drift on the applicable normal uncertainty allowances in Reference 5.A.b. Therefore, any impact on the proposed channel check limit in References 5.M.a, 5.M.b and 5.M.c will be evaluated as a result of Corrective Action #2. Corrective Action #3 of PIP 0-09-4103 has been issued to evaluate the existing RPS RC Pressure Channel Check acceptance criteria in PT/_/A/0600/001 (Reference 5.D) in comparison with the above results as they may be too permissive for use during extended fuel cycles.
OSC-9771, Rev. 1 Page 43
8.0 CONCLUSION
S/RESULTS The purpose of this calculation is to perform the As-Found/As-Left (AFAL) Drift Analysis for the Reactor Protection System (RPS) Reactor Coolant System Pressure instrument loops. The AFAL calibration data will be obtained through review of completed instrument procedures (Reference 5.C). This calculation was designated a QA Condition I Calculation because the RPS RC Pressure instrumentation is relied upon to trip the reactor during certain design basis events. The RPS RC Pressure Trip Setpoints are defined by Technical Specification Section 3.3.1, Table 3.3.1-1, Functions 3, 4, 5 and 11. I, Section 1.4 shows that only RPS RC Pressure transmitter is available for and requires an AFAL Drift Analysis. All other instrumentation is accounted for as part of the Digital RPS and ESFAS Replacement modifications as is explained in Section 1.1. The methodology used in this analysis is defined in Reference 5.G and summarized in Section 3.0. The references used in this analysis are shown in Section 5.0. The assumption and design inputs used in this analysis are shown in Sections 6.1 and 6.2, respectively. The 18 month Analyzed Drift (AD) value, determined with a 95% confidence and 95% pr--ob-ba-i~ity, was calc-ufed-i--Se-gtio-n-7.-3.3--n--d-is-shown be-low. RPS RC Pressure Transmitter AD: +/- 1.3 psi (bias) to +/- 8.6 psi (random). The extended cycle Analyzed Drift (ADE) value, determined with a 95% confidence and 95% probability, was calculated in Section 7.4.1 and is shown below. RPS RC Pressure Transmitter ADE: +/- 2.6 psi (bias) to +/- 11.1 psi (random). The extended cycle Analyzed Drift values are applicable to a 30 month calibration interval and may be used in the instrument uncertainty calculation (Reference 5.A) in accordance with the ONS Setpoint Methodology (Reference 5.B.a). Corrective Action #2 of PIP 0-09-4103 has been issued to evaluate the effects of the extended cycle Analyzed Drift on the RPS RC Pressure Total Loop Uncertainties (both References 5.A.a and 5.A.b) and to include pressure M&TE errors in the existing RPS RC Pressure uncertainties (Reference 5.A.a). Corrective Action #3 of PIP 0-09-4103 has been issued to evaluate the existing RPS RC Pressure Channel Check acceptance criteria in Reference 5.D and the proposed channel check limit for the replacement Digital RPS/ESFAS (References 5.M.a, 5.M.b and 5.M.c) in comparison with the above results as they may be too permissive for use during extended fuel cycles.
OSC-9771, Rev. 0 Page 44 8.1 NRC GL 91-04 Issue I Resolution 0 Issue 1 of Enclosure 2 to NRC GL 91-04 states:
"Confirm that instrument drift as determined by as-found and as-left calibration data from surveillance and maintenance records has not, except on rare occasions, exceeded acceptable limits for a calibration interval."
Section 7.5 confirms that the RPS RC Pressure transmitters have 'rarely' exceeded Acceptable Limits as defined by this issue. Issue 1 of Enclosure 2 to NRC GL 91-04 has been completely addressed for the RPS RC Pressure Transmitters in this Drift Analysis. 8.2 NRC GL 91-04 Issue 2 Resolution Issue 2 of Enclosure 2 to NRC GL 91-04 states:
"Confirm that the values of drift for each instrument type (make, model, and range) and application have been determined with a high probability and a high degree of confidence. Provide a summary of the methodology and assumptions used to determine the rate of instrument drift with time
____ _ based-upon-historical-plant-calibration-data."- Sections 1.0 and 1.4 contain the make and model numbers for each of the RPS RC Pressure instruments being evaluated in this analysis. Sections 1.1 and 1.3 define the applicability of the instruments to this analysis. Design Input 6.2.1 defines the effort and scope of the data retrieval process for these instrument strings. Based on this effort and scope, the magnitude of the instrument drift determined herein is of a high probability and a high confidence. The methodology and assumptions used in the Drift Analyses are defined in Reference 5.G and summarized in Section 3.0. Issue 2 of Enclosure 2 to NRC GL 91-04 has been completely addressed for the RPS RC Pressure Transmitters in this Drift Analysis. 0
OSC-9771, Rev. 0 Page 45 8.3 NRC GL 91-04 Issue 3 Resolution 0 Issue 3 of Enclosure 2 to NRC GL 91-04 states:
"Confirm that the magnitude of instrument drift has been determined with a high probability and a high degree of confidence for a bounding calibration interval of 30 months for each instrument type (make, model number, and range) and application that performs a safety function.
Provide a list of the channels by Technical Specifications section that identifies these instrument applications." Sections 1.2 and 1.3 describe the safety function of the RPS RC Pressure - High, Low and Variable Bistable strings and provide the applicable Technical Specifications Section. Sections 1.0 and 1.4 provide the make and model numbers for each of the RPS RC Pressure instruments being evaluated in this analysis. Section 7.2 provides the instrument span. For a complete list of channels by Technical Specifications Section, see Attachment 9.2 of Reference 5.G. The Analyzed Drift is determined with a high probability and a high degree of confidence for a bounding calibration interval of 30 months in Section 7.4.1. Issue 3 of Enclosure 2 to NRC GL 91-04 has been completely addressed for the RPS RC Pressure Transmitters in this Drift Analysis. 0 0
OSC-9771, Rev. 0 Page 46 8.4 NRC GL 91-04 Issue 4 Resolution Issue 4 of Enclosure 2 to NRC GL 91-04 states:
"Confirm that a comparison of the projected instrument drift errors has been made with the values of drift used in the setpoint analysis. If this results in revised setpoints to accommodate larger drift errors, provide proposed Technical Specifications changes to update trip setpoints. If the drift errors result in a revised safety analysis to support existing setpoints, provide a summary of the updated analysis conclusions to confirm that safety limits and safety analysis assumptions are not exceeded."
Section 1.2 and 1.3 describe the safety limits of the applicable RPS RC Pressure instrument strings. Section 7.5 shows that the values of drift used in the current setpoint analysis are acceptable (by confirming that they 'rarely' exceed the Acceptable Limits as defined by Issue 1). Section 7.5 also shows some inconsistencies between the existing loop configuration uncertainties and the ONS Instrument Uncertainty Methodology (EDM-102). Section 7.6.1 shows that the values of drift used in the setpoint analysis require evaluation with respect to the extended cycle Analyzed Drift. The Analyzed Drift is determined with a high probability and a high degree of confidence for a bounding calibration interval of 30 months in Section 7.4.1. Corrective Action #2 of PIP 0-09-4103 has been i-s-ied tolevahite the*-effects oft -e--xten-de-cd-ycle Analyzed Drift-on-the-RPS-RC -... Pressure Total Loop Uncertainties (both OSC-4048 and OSC-8828) and to ensure M&TE uncertainties in OSC-4048 are consistent with the M&TE used in the instrument calibration procedure (Reference 5.C). Issue 4 of Enclosure 2 to NRC GL 91-04 has been completely addressed for the RPS RC Pressure Transmitters in this Drift Analysis and Corrective Action #2 of PIP 0-09-4103. 8.5 NRC GL 91-04 Issue 5 Resolution Issue 5 of Enclosure 2 to NRC GL 91-04 states:
"Confirm that the projected instrument errors caused by drift are acceptable for control of plant parameters to affect a safe shutdown with the associated instrumentation."
Section 1.2 and 1.3 shows that the RPS RC Pressure instrument strings are not relied upon for safe shutdown. Issue 5 of Enclosure 2 to NRC GL 91-04 has been completely addressed for the RPS RC Pressure Transmitters in this Drift Analysis.
OSC-9771, Rev. 0 Page 47 8.6 NRC GL 91-04 Issue 6 Resolution Issue 6 of Enclosure 2 to NRC GL 91-04 states:
"Confirm that all conditions and assumptions of the setpoint and safety analyses have been checked and are appropriately reflected in the acceptance criteria of plant surveillance procedures for channel checks, channel functional tests, and channel calibrations."
Sections 7.6.2 through 7.6.4 show a comparison of the extended cycle Analyzed Drift, instrument uncertainties and plant surveillance acceptance criteria. Based upon this comparison, Corrective Action #3 of PIP 0-09-4103 has been issued to evaluate the existing RPS RC Pressure Channel Check acceptance criteria in Reference 5.D and the proposed channel check limit for the replacement Digital RPS/ESFAS (References 5.M.a, 5.M.b and 5.M.c). Issue 6 of Enclosure 2 to NRC GL 91-04 has been completely addressed for the RPS RC Pressure Transmitters in this Drift Analysis and Corrective Action #3 of PIP 0-09-4103. 8.7 NRC GL 91-04 Issue 7 Resolution Issue 7 of Enclosure 2 to NRC GL 91-04 states:
"Provide a summary description of the program for monitoring and assessing the effects of increased calibration surveillance intervals on instrument drift and its effect on safety."
Issue 7 of Enclosure 2 to NRC GL 91-04 will be addressed as part of the ongoing calibration surveillance procedure review program. Once the 24-month Technical Specification surveillance intervals have been approved and implemented, this calibration surveillance procedure review program will verify that future loop/component As-Found/As-Left calibration values do n6t exceed those acceptable limits determined in the Drift Evaluations and associated instrument uncertainty calculations as revised to reflect a 30 month maximum calibration interval, except on rare occasions.}}