View source for BVY 03-115, Technical Specification Proposed Change No. 257 Implementation of Arts/Smella at VYNPS Supplemental Information and Proposed Allowable Value, Attachment 2, Calculation VYC-0693A

{{Adams
| number = ML033600061
| issue date = 12/11/2003
| title = Technical Specification Proposed Change No. 257 Implementation of Arts/Smella at VYNPS Supplemental Information and Proposed Allowable Value, Attachment 2, Calculation VYC-0693A
| author name = Thayer J
| author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000271
| license number = DPR-028
| contact person = 
| case reference number = BVY 03-115
| document report number = VYC-0693A
| document type = Calculation, Technical Specifications
| page count = 96
}}

=Text=
{{#Wiki_filter:Docket No. 50-271 BVY 03-115 Attachment 2 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 257 Calculation VYC-0693A - APRM Neutron Monitoring Trip Loops

VY CALCULATION TITLE PAGE VX'C-0693A                                2                               NIA                           N/A VY Calculation Number            Rcvision Number                VXendor Caleulation Number              Revision Numiaber

==Title:==
APRM Neutron Monitorinq Trip Loops QA Statwts:           ER  SG     O NNS    O   OQA               Operiting Cycle Nunmber*         N/A I Operating Cycie Number should only he entered here If the results of the calcualation onlv apply during a spccitic The operating cycle otherwise enter "NMA".
Cnalculation Supports A Design Change/Specification? (3 Ves El No                      4 2003-029 v'yt)cN 1yn MIamspec Nte.
Implementation Required? IZ'Ves 4gC                                        CAlculation DUne ns a Study Only?      0 Yes   0   No Sarety Evaluation Number:               N/A_
Superseded Cilculation Number, lille andt Revision:_ VYC- 693A Rev. 1 APRM Neutron Monitoring Trip Loops For Revisions: List CCNs, I[is. or SAs incorporated/supersedted by this revision:
Computer Code(s):                 NIA Are there open tiems in this enleulation/revlsion?           7 Yes 0     No Review and Approvel: (Print and Sig Name)
Preparer: JerryVnss                                    _                          Date:      II/ I/2003 Interdisciplinc Reviewer(s%:t     See Attafilment 7.7                            Date:_     _ _
Independent Revievers(v Kirk Meljon                                       __      Date:      11/19/2003 Appruvcd: -7Z                    VIFe7g        /7           ki                               :L/./d3 Accepted (only Tor AP 0017 enceflations plrformed by s'cndors)                        N/A Dnte:        ,'    .-
Fimnl Turnover to DCC (Section 2):
: 1)        All upen items. if nny. have been closed.
: 2)         Implementation Confirmotion (Section 2.3.4)                   -     -
Q Calculation accurately reflects existing plnnt cv'ntigritioor.
(confirmation method indicated below)             -
O Walkdown           a   As-Built input review    X        cusslo OR 3   N/A, calculation does not reflect existing plpant onfi      !fia
: 3)        Resolution of documents identified In the Design Output acumen                 tinn urVYAPf 0017.07 las hren initiated as required (Section 2.3.6, 23.7)
Printed Name                                Signature              _DAte_
Page I or_             Pages*
for ctlculaitions peralcrmtxl using AP 0017 thIs schc numbcroulprages in thlbodv nrtiliu fl Luliitiuil.                vYAPIF 0017.01 lFor vendor ciaculations. this is the number orpagesi ol Al' 0017 formr' udded.                                         AP t(l 17 Rev. X (Title page, rcvicw forms. dcaut shects. 50.S9. tcl.)                                                              Past I oil I.l'C 4/2

VY CALCULATION DATABASE INPUT FORM Place this form in the calculation package immediately following the Title page or CCN form.
_____VYC-693A                          _       2                                     N/A                                            N/A VY Calculation/CCN Number            Revision Number                 Vendor   Calculation    Number                        Revision Number Vendor Name:                                              PO Number Originating Department:
Critical References Impacted: Cl UFSAR          Q DBD [ Reload. "Check" the appropriate box if any critical document is identified in the tables below.
EMPAC Asset/Equipment ID Number(s):
EMPAC Asset/System ID Number(s):
Keywords:
For Revision/CCN only Are deletions to General References, Design Input Documents or Design Output Documents required? El Yest Z No Design Input Documents and General References - The following documents provide design input or supporting information to this calculation. (Refer to Appendix A, sections 3.2.7 and section 4)
Significant      +'"'    Critical Reference                                 REV                                                                                                     Difference     Affected Reference ft             ** DOC #       X                                  ***Document Title (including Date, if applicable)                          Review tt      Program     (/)
6.15      GE-NE-0000-0012-                     May 2003 Project Task Report "Entergy Nuclear Operations Incorporated Vermont                       N/A          N/A 0531-01-01                           Yankee Nuclear Power Station ARTS/MELLLA" Task T0506: NSSS TS Instrument Setpoints.
6.16      GE-NE-0000-0016-              Qj     August 2003 Project Task Report "Entergy Nuclear Operations Incorporated                            N/A          N/A 5688-01                              Vermont Yankee Nuclear Power Station Extended Power Uprate" Task T0506:
NSSS TS Instrument Setpoints.
6.27      VYC-0690                   2         Recirculation Flow Loop Uncertainties to APRM 6.29      NEDC-33089P                          "Vermont Yankee Nuclear Power Station APRM/RBM/Technical Specifications Maximum Extended Load Line Limit Analysis (ARTS/MELLLA)," March 2003 6.30      Nl DC-33090P               0         "Safety Analysis Report for Vermont Yankee Nuclear Power Station Constant Pressure Power Uprate," September 2003 626       OP-2429                    14        Recirculation Flow System Baseline Data Collection and Instrument Calibration.
6.17      GE Performance             I         "Flow Control Trip Reference (FCTR) Card".
Specification 25A5903 6.31      BVY 03-23                  0         March 20,2003, Technical Specification Proposed Change No. 257 Implementation of ARTS/MELLLA 632_____       0S1
_______________________                 Wx.                3       c        iPat 6.32      BVY 03.80                  0          September 10, 2003, Technical Specification Proposed Change No. 263 Extended Power Uptate. ________________
eA69 z OF V'T          i:.:.:
1tr               t: ".:

APRM/RBM Neutron Monitoring Trip Loops                                                                   VYC-693A, Revision 2 Design Output Documents - This calculation provides output to the following documents. (Refer to Appendix A, section 5)
                                                                                                                                                                +* ****      tttCritical Reference                                                                                                                                   Affected         Reference 0        ** DOC #        REV #                            Document Title (including Date, if applicable)                              Program             (V) 6.25        OP 4308           21         APRM Monitor Calibration.
                   =~~~I                     I=
                   .~~~
* Reference #-          Assigned by preparer to identify the reference in the body of the calculation.
               ** Doc # -              Identifying number on the document, if any (e.g., 5920-0264, G191172, VYC-1286)
               *** Document Title -    List the specific documentation in this column. "See attached list" is not acceptable. Design Input/Output Documents should identify the specific design input document used in the calculation or the specific document affected by the calculation and not simply reference the document (e.g., VYDC, MM) that the calculation was written to support. If a DBD is used as a general reference, include the most current interim change number after the title.
               **** Affected Program - List the affected program or the program that reference is related to or part of.
tt                      If "yes," attach a copy of "VY Calculation Data" marked-up to reflect deletion (See Section 3.1.8 for Revision and 5.2.3.18 for CCNs).
If the listed input is a calculation listed in the calculation database that is not a calculation of record (see definition), place a check mark in this space to indicate completion of the required significant difference review. (see Appendix A, section 4.1.4.4.3). Otherwise, enter         ... i t11*
ttt                     'NIA."
If the reference is UFSAR, DBD or Reload (IASD or OPL), check Critical Reference column and check UFSAR, DBD or Reload, as appropriate, on this form (above).
Vennont Yankee Design Engineering                                                                     Page 3 of 29 A\.,, . ... ;.       .

TABLE OF CONTENTS
: 1. PURPOSE ..................                                 I..........................................6 1.1   CALCULATION OBJECTIVES .............................................................                                                                                 6 1.2   SYSTEM AND COMPONENTS .............................................................                                                                                  7 1.3   INSTRUMENT LOOP FUNCTION .............................................................                                                                               7 2   METHODS AND ASSUMPTIONS .............................................................                                                                                  8 2.1   GOVERNING PROCEDURES AND PROGRAMS .............................................................                                                                      9 2.2   CRITERIA .............................................................                                                                                               9 2.3   ASSUMPTIONS ............................................................                                                                                            12 3   INPUTDATA ............................................................                                                                                                13 3.1   PROCESS, Loop DATA AND ANALYTICAL Lm s ...............................................................                                                              13 3.2   ENVIRONMENTAL CONDITIONS ............................................................                                                                               14 3.3   PRIMARY ELEMENTS ND-2-1-104 DATA .............................................................                                                                      14 3.4   LPRM DATA .............................................................                                                                                             15 3.5   APRM A, B, C, D, E, F, DATA ............................................................                                                                            15 3.6   FLOW BIAS ERROR DATA ............................................................                                                                                   15 4   CALCULATION DETAIL ............................................................                                                                                       16 5   RESULTS AND CONCLUSIONS ............................................................                                                                                  16 5.1   ALLOWABLE VALUE ............................................................                                                                                        16 5.2   SETPOINTEVALUATION ............................................................                                                                                     17 5.3   CALIBRATION AND TESTRESULTS ............................................................                                                                           18 5.4   CALCULATION REVIEW AND IMPACT CONSIDERATION ............................................................                                                           20 5.5   

==SUMMARY==
OF REQUIREMENTS ............................................................                                                                               21 5.6   

==SUMMARY==
OFRECOMMENDATIONS........................................................................................................................21 6   REFERENCES ............................................................                                                                                              28 7     ATTACHMENTS......................................................................................................................................................29 7.1   LOOPDIAGRAM[ I PG] ............................................................                                                                                    29 7.2   CALCULATION DETAIL (B 1THROUGH B4) [8 PGS] ............................................................                                                            29 7.3   DESIGN SPECICATION 22A1366, REV. 3, "NEUTRON MONITORING SYSTEM" [2 PGS] ............................................... 29 7.4   DESIGN SPECIFICATION -DATA SHEET22AI366AF,REV. 1, "NEUTRONMONITORING SYSTEM"[1 PG) ..................... 29 7.5   DESIGN AND PERFORMANCE SPECIFICATION 175A1 259, REV. 1, "APRM" [3 PGs] ..................................................... 29 7.6   GE PERFORMANCE SPECIFICATION 25A5903 REV. l, "FLow CONTROL TRIP REFERENCE (FCTR) CARD [ 23 Po] ...... 29 7.7   AP-00 17 FORMS AND INTERDEPARTMENTAL REVIEW FORM [6 PGS] ........................................................................... 29 Vermont Yankee Design Engineering                                                                                                                  Page 4 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                 VYC-693A, Revision 2 Approval Rev. No.            Date                             Reason & Description of Change 0                              Initial issue, Reflects new methodology described in Instrument Uncertainty and Setpoints Design Guide, Rev.
0 This sub-calculation (VYC-693A) only addresses the associated trips, with the analog output uncertainties remaining in the parent calculation (VYC-693).
1                              Revised to allow the use of N=44 in the RBM flow bias equation (Setpoint < 0.66(W-AW) + N), and to reflect the use of M&TE to set the Flow Bias value in testing the RBM rod blocks. References to any specific operating cycle or COLR report were removed since this calculation is valid for any cycle where the value of N is between 42 and 44.
2                              Incorporated VYC-693A CCNs 1, 2, 3 and 4. CCN 2 attachment M and table revisions had no impact on this revision of the calculation since the CCN was based on the flow bias equations used prior to ARTS/MELLLA or EPU.
This revision includes the Analytical Limits and calculates Allowable Values (ITS) Trip Setpoints and As-Found Tolerances (CTS) to support ARTS/MELLLA and EPU.
The APRM Rod Blocks have been removed from the Technical Specifications. The Rod Block Monitor has been maintained in Technical Specifications; However, the Rod Block Monitor will be treated as an indicated value (without instrument error) for settings.
: 4.                    4
: 4.                    I Vermont Yankee Design Engineering                                                    Page 5 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                                 VYC-693A, Revision 2
: 1.       PURPOSE 1.1      Calculation Objectives This calculation has been developed in support of the Vermont Yankee Setpoints program and covers the APRM/LPRM (Average Power Range Monitor/Local Power Range Monitor) neutron monitoring loops. This calculation has the following major objectives:
: 1)      Document the instrument loop functions and the basis for the setpoints and operator decision points associated with those functions.
: 2)       Establish the total loop uncertainty for each increasing' Setpoint and verify consistency with the design basis
: 3)       Calculate the limiting setpoints and operator decision points.
: 4)       Evaluate the adequacy of existing Setpoint Administrative Limits and procedural decision points.
: 5)       Provide As-Left and As-Found tolerances for use in instrument calibration and functional test procedures. Verify and document process corrections, instrument scaling, and calibration methods. The errors determined in this calculation are based on the vendor defined operating characteristics.
: 6)      This calculation does not include evaluations of the analog indicators or recorder functions. The accuracy of the trip functions determined by this calculation will be used as input for generic evaluations for alarm response, operating procedures, off normal operating procedures and EOP impact.
Low (decreasing) setpoints are not reviewed. They are indicative of a gross failure. Therefore, it is not necessary to determine uncertainty.
Vermont Yankee Design Engineering                                                                    Page 6 of 29 S

                                  --                                       ~~~~~~~~~~~~~~~~
APRM/RBM Neutron Monitoring Trip Loops                                             VYC-693A, Revision 2 1.2   System and Components This calculation applies to the Power Range Monitoring Instrumentation of the Neutron Monitoring System. The specific components to be addressed are:
Table 1: System Components REF. TAG            lACK        l SYS   DESCRIPTION       lIFG. MODEL NO.      CWD NUMBER          CABINT 6.18   ND-2-1-104      In-Core      NM    LPRM Detector       GE    N/A            674,675 (80 items) 6.18   LPRM            9-14         NM    Local Power Range   GE     135B9824G2    676,676A, Monitor                                  677,677A 6.18   APRM A, C,      9-14         NM    Average     Power   GE    920D453GI      678, 679, E, B, D, F                         Range Monitor             920D453G2      680, 688, 692, 693 1.3   Instrument Loop Function Attachment A has a simplified loop diagram of the instruments and components described below.
1.3.1   Normal Operations During normal operation the APRMs provide the control room operators with indications of the average reactor power from about two percent to 125 percent via recorders on the operators console. This analog information is also provided to the plant computer. In addition, the APRMs are capable of generating trips when various conditions are exceeded. These trips are:
* Scram on APRM Upscale
* Scram on APRM Downscale (Run Mode)
* Scram on APRM Inoperative
* Scram on APRM Upscale when the RMSS is not in Run (Reduced)
* Rod Block on APRM Upscale
* Rod Block on APRM Downscale
* Rod Block on APRM Upscale when the RMSS is not in Run (Reduced)
During normal operation the RBMs provide the control room operators with indications of the local average power immediately surrounding a control rod that has been selected for withdrawal. The RBM promotes controlled rod withdrawal by issuing rod withdrawal block signals if the reactor operator does not respond correctly to prompts requiring operator action. The RBM issues rod withdrawal block signals on:
* RBM Upscale
* RBM Downscale Vermont Yankee Design Engineering                                                 Page 7 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                VYC-693A, Revision 2 The Rod Blocks associated with APRM and the Rod Block Monitor are not credited for plant protection. The APRM Rod Blocks have been removed from Technical Specifications (and placed in the VY Technical Requirements Manual The Rod Block Monitor is maintained in Technical Specifications; however, the setting for the RBM is treated as an indicated values (without instrument error applied to the setting). Therefore, only the APRM trips will be evaluated in this calculation.
The purpose of the APRM flow biased rod block function is to avoid a condition that would require Reactor Protection System action if allowed to proceed. The APRM flow biased rod block setting is selected to initiate a rod block before the APRM high neutron flux scram setting is reached. The APRM flow biased rod block setpoint value listed in the TRM is the maximum nominal trip setpoint allowable. Calibration tolerances have been established for this setpoint that will render the setpoint acceptable above or below the nominal value. The uncertainty associated with the difference between the APRM flow biased scram and rod block functions is limited to the uncertainty associated with the trip circuitry.
Common equipment (such as detectors, LPRMs, flow input and averaging circuits) will affect both functions equally.
VY has implemented long-term thermal hydraulic stability solution Option I-D.
Option I-D is only applicable to plants that can demonstrate that core wide mode instability is the predominant mode and regional mode instability is not expected.
Solution application includes demonstrating that the APRM High Flux (Flow Bias) scram line, considered an analytical limit, provides adequate Safety Limit MCPR protection.
1.3.2 Functions During an Accident The APRMs are assumed to provide the scram initiation signal (120 % power) for the mitigation of the Control Rod Drop Accident, which, according to Reference 6.4, Section 14.6.2, is only of concern when the reactor is operating at less than the RWM Low Power Setpoint (LPSP).
1.3.3   Post-Accident or EOP Functions The APRMs are not required for Post Accident Functions. The APRMs applicability to the EOPs will be addressed outside of this calculation.
2     METHODS AND ASSUMPTIONS This Calculation has been prepared in accordance with the Governing Procedures and Programs listed in step 2.1. Standard methods employed in this calculation are explained in the "Vermont Yankee Instrument Uncertainty and Setpoints Design Guide" [Ref.6.1]. This calculation is performed using the Class 1 graded approach since one of the functions (reactor scram) performed by the APRM loops is classified as Class 1, Nuclear Safety Related.
Vermont Yankee Design Engineering                                                    Page 8 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                VYC-693A, Revision 2-2.1    Governing Procedures and Programs 2.1.1 VermontYankecInstrumentUncertaintyandSetpointsDesignGuide.(Ref6.1) 2.1.2 VennontYank-eeEngineeringProcedureAP-0017,CalculationsandAnalyses (Ref. 6.9).
2.2    Criteria 2.2.1 Analytical Limits and Technical Specification Limits Ile Analytical Limits (AL) for the APRM Scram Flow Bias and Fixed trip are established per the Rod Drop Accident and Core Stability Analysis, and are defined in Ref. 6.15 for ARTS/MELLLA conditions and 6.16 for Extended Power Uprate conditions. This AL value will be used to establish Limiting Setpoints (LSp) and an Allowable Value (AV) for use in the Technical Specifications (TS) as discussed below.
This calculation will use ISA-S-67.04.02 Method I for combination of errors to determine a Trip Setpoint and an Allowable Value for Technical Specification values associated with APRM Flow Bias and Scram setpoints. The Limiting Trip Setpoint and the Allowable Value for a process increasing to a limit will be calculated as follows:
AV              AL-effective uncertainty for all devices and errors not confirmed during surveillance testing.
LSp             AV - effective uncertainty for testing conditions, including devices tested only.
LSp <           AV - (CT, + CT2 + CT,,) Confirmation of margin between LSp and AV.
All terms are as currently defined in the VY Setpoint Design Guide.
2.2.2    Numerical combinations for the calculations of instrument error, calibration error, loop error, effective error and other associated values have been calculated using Microsoft Excel. Representative calculations in Attachment(s) B were manually verified using a hand calculator, Microsoft Excel stores numbers with at least 15 digits of accuracy, all calculation outputs displayed within this calculation are rounded from the values stored by Excel. Rounding errors induced by Excel are assumed to be negligible within Us calculation.
2.2.3    No errors were found in the manual verification of the calculations performed with the Software in Attachment B. Physical evidence of the review is provided by check marks or other indications'next to each verified calculation. Where multiple calculations are generated by copying cells or formulas selected samples have been verified.
2.2.4    Technical Specification Table 4.1.2 requires the performance of a Heat Balance, for calibration of the APRM output signal, once every 7 days. The calibration of the APRMs to CoreThermal. Power (CTP) is performed under OP-4400. As a part of this procedure, the individual APRM gains are adjusted such that the individual APRMs read conservatively to the adjusted % rated CT? (+2, -00/o).
Vermont Yankee Design Engineering                                                   Page 9 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                VYC-693A, Revision 2 The adjustments made to the APRM gains automatically compensate (normalize) the LPRM detector/amplifier output signal. Therefore, since the heat balance is perfomed every 7 days, the amount of LPRM drift that needs to be considered is only 8 days (7 days + 25% extension). The current LPRM drift value is valid for 700 hours. However, since there is insufficient information to estimate the reduction in this drift value for 8 days, the 700 hour drift value will be used in the calculation.
2.2.5   Primary Element Accuracy (PEA)
APRM Channel PEA is a combination of sensor sensitivity and sensor non-linearity uncertainties.
The sensitivity of the detectors decreases with neutron fluence. From Reference 6.13, Section 4.5, the average sensitivity loss, and its 2-sigma variation, for all GE LPRM detectors has been determined to be:
Sensor Sensitivity Loss = -0.33%        (bias term)
                                                         +0.20%      (random term)
The detector non-linearity and its 2 sigma variation (in the power range) has been determined to be:
Sensor Non-linearity = -0.49%           (bias term)
                                                      +/-1.0%          (random term)
The first part of these detector errors represent bias type errors which apply to all detectors, whereas the second part are random errors that represent variability amongst sensors. Assuming a worst case scenario where the APRM has the minimum number of operational detectors, the PEA, which on a percent of power basis is simply obtained by adding the bias terms and taking the SRSS of the random terms, is calculated below. In the calculation, the random error is reduced by the square root of the minimum number of operable LPRMs to one APRM channel which is 9 per Reference 6.7, Table 3.1.1, Note 5.
PEA =(0.33+0.49)+/-in)/(0.202 +12))
PEA = -0.82+/- 0.34%RP 2.2.6 Process Measurement Accuracy (PMA)
APRM PMA is a combination of APRM tracking error and the uncertainty due to neutron noise. From Reference 6.4, Section 14.5.1.3.1, the most severe event for which the APRMs are assumed to provide the scram signal is the Closure of All Main Steam Line Isolation Valves with failure of the valve position scram. Reference 6.13, Section 4.5 states that for the MSIV closure transient event, the APRM tracking error is 1.1 1% and the uncertainty due to neutron noise is typically 2.0%.
The tracking error is the uncertainty of the maximum deviation of APRM readings with LPRM failures or bypasses during a power transient. The neutron noise is the global neutron flux noise in the reactor core with a typical dominant Vermont Yankee Design Engineering                                                    Page 10 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                VYC-693A, Revision 2 frequency of approximately 0.3 to 0.5 Hertz and typical maximum peak-to-peak amplitude of approximately 5 to 10 percent.
PMAS = k(2.o 2 + 1.112 ) = 2.29%RP 2.2.7   The Flow Control Trip Reference Card (FCTR) for the APRM fixed and flow biased scrams is being replaced. The replacement card is designed to operate with a 1% maximum error signal and 0.1% timing accuracy (Ref. 6.17). The 1% error signal includes both device accuracy and drift for a 36-month interval. General Electric has provided additional information (Attachment 7.7) indicating that the reference accuracy (or setting tolerance) for the FCTR is 0.5% of calibrated span.
Control Room (CR) Indication (FI-2-159A, B and FR-2-154) is scaled for a flow rate of 041,800 GPM. Rated Recirculation Drive Flow (100%) is defined as the required Drive Flow to achieve 48 MPPH (Reference TS 2.1.A.l .a). Such things as core design, changes in core and piping resistance, jet pump fouling, etc, affect the relationship between Core Flow and Drive Flow. Therefore, since the rated recirculation drive flow value could change, the percentage of rated flow for CR flow indication will vary. OP 2429 normalizes the total recirculation drive flow (output of summers FSUM-2-l lOA&B) such that the input to the APRM system is 125% of rated flow (as determined by OP 2429). This is consistent with functional testing of the APRM Flow Bias Setpoints and flow indication obtained from the APRM system (chosen via selector switch). Because of this normalization the spans between the drive flow input (VYC-690 errors) and the core flow input are assumed to be equal.
2.2.8   Technical Specification Table 4.1.2 requires the performance of a heat balance, for calibration of the APRM output signal, once every 7 days. The calibration of the APRMs to Core Thermal Power (CTP) is performed under OP 4400. The procedure begins by the calculation of CTP by performing an energy balance on the Nuclear Boiler System. Next, % rated CTP is determined (CTP/Rated CTP MWth
* 100). Then % rated CTP is divided by the applicable scale factor to find the adjusted % rated CTP. Finally, the individual APRM gains are adjusted such that the individual APRMs read conservatively to the adjusted % rated CTP (+2, -
0%). The adjustments made to the APRM gains automatically compensate (normalize) the LPRM detector/amplifier output signal. Therefore, since the heat balance is performed every 7 days, the amount of LPRM drift that needs to be considered is only 8 days (7 days + 25% extension). The uncertainty associated with the heat balance (2% of Reactor Power) is included in the transient analysis (REF. 6.19). Therefore, this uncertainty is not included in this uncertainty calculation.
2.2.9   Calibration tolerance for reactor flow biased power settings are + 0.5% CS or (0.625% RP). The tolerances for trips are +0.4% CS (0.5% RP) per Ref. 6.25 and 6.23.
Vermont Yankee Design Engineering                                                    Page 11 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                VYC-693A, Revision 2 2.3    Assumptions 2.3.1   Calibration of instruments is assumed to be at a temperature within the ranges shown in the following table.
Table 2: Plant Area(s) l Plant Area                                 I Minimum I Maximum Control Room                                 60 0 F       180 OF 2.3.2   The temperature variation within a cabinet is the same as the variation of the room in which it is located. The temperature difference between the room and the cabinet is therefore constant. Calibration data are collected with the equipment at the operating temperature of the cabinet.
2.3.3   The vendor does not state a separate value for Humidity Effect (HE). Therefore, it is considered to be included in the accuracy and drift terms.
2.3.4   OP4305 does not give a tolerance for setting the value of the flow signal, because the flow signal is adjusted as close as possible using M&TE. This calculation assumes that only M&TE with a total accuracy of better than 0.25% of reading will be used to adjust the flow signal. Therefore, this uncertainty is assumed to be 0.25 %. This 0.25 % will be combined with the random portion of the VYC-690 flow input. This signal error will then be converted to %RP before being combined for each of the different power to flow lines. However, since the M&TE error affects the overall accuracy and the acceptance criteria for the flow bias setpoints, M&TE with accuracy of 0.05% of span will be used for setting the flow signal value.
2.3.5   All of the Power Range Neutron Monitoring System electronic equipment affected by this calculation are located in areas considered to be mild environment (control room). The LPRM detectors are the only components exposed to high radiation and they were designed for this purpose. Therefore, there are no Radiation Effects (RE) applicable to this calculation.
2.3.6   The APRM scrams are not assumed to operate for safe shutdown or for other seismic events. For operational basis earthquakes, this calculation assumes that the APRMs, LPRMs and trip functions will be recalibrated prior to continued operation. Therefore, seismic error for Neutron Monitoring is not considered in this calculation.
2.3.7   Dead Band (DB) or Readability Uncertainty (RD) are only applicable to that portion of a calculation involving indicators and recorders. Therefore, they do not apply to this calculation.
Vermont Yankee Design Engineering                                                  Page 12 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                   VYC-693A, Revision 2 2.3.8   Temperature Effect (TE) is not provided as a separate term by the vendor so it is assumed to be included in one of the given accuracy or drift terms.
2.3.9   The Barometric Pressure Effect (PB) is not applicable to this calculation (Section 3.6.9 of Ref. 6.1).
2.3.10 None of the Process Static Pressure Effects (SP) are applicable to this calculation (Section 3.6.13 of Ref. 6.1).
2.3.11 Power Supply Voltage Effect (VE) is considered to be included in the accuracy and drift terms since the vendor does not give a separate value for VE.
2.3.12 VYC-1 758 (Reference 6.20) shows DNM's available to support the APRM calibration with total device error of better than +-0.05%CS (1 0 VDC Range).
Therefore, the SRSS of 2 DMM's required for the calibration per Rcf. 6.25 result in an M&TE uncertainty of +/-0.07 1% CS.
2.3.13 The neutron monitoring system is located in the control room with the exception of the sensing devices, which are located in the reactor. Therefore, unless otherwise stated, this calculation -will use the set of specifications related to the Control Room envirom-nent in Ref 6.1.
2.3.14 Technical Specification Table 3.1.1 defines the Limit for APRM High Flux Reduced as equal to 15 % RP. This value has been assumed to be the Analytical Limit for this calculation.
3     WPUT DATA Data used to calculate loop uncertainties, process corrections, setpoints, and decision points are tabulated below with the applicable reference or basis 3.1     Process, Loop Data and Analytical Limits Presented below are the input values required to calculate the Limiting Setpoints (Analytical Limits and those parameters such as calibration frequency that are common to all loop components).
Vermont Yankee Design Engineering                                                      Page 13 of 29

                 .  .. .. . .. . : . . . . . ....  " ,::.:  !.., ': 1 : ., I - . , .':!' . , :. :. I1.                           - .- ~ , ,-::-. ? :':.:. .~ . Z APRM/RBM Neutron Monitoring Trip Loops                                                                             VYC-693A, Revision 2 Table 3: Process Data and Analytical Limits Basis                             Description                                                   Data Ref. 6.3                          Process Span (PS)                                             0 to 125 % RP Analytical Limits ARTS/MELLLA                             APRM High Flux Scram (Two Loop Ops)
Reference 6.15                    Core Flow 0 to < 31.1 %                                       <0.4Wd+64.4%
Core Flow 31.1 to < 54.0 %                                    < 1.28Wd+37.0%
Core Flow 54.0 to < 75 %                                      < 0.66Wd+70.5%
Core Flow> 75%                                                Maximum of 120%
APRM High Flux Scram (Single Loop Ops)
Core Flow 0 to < 39.1 %                                       < 0.4Wd+61.2%
Core Flow 39.1 to < 61.9 %                                    < 1.28Wd+26.8%
Core Flow 61.9 to < 83.0 %                                    < 0.66Wd+65.2%
Core Flow >83%                                                Maximum of 120%
Extended Power                          APRM High Flux Scram (Two Loop Ops)
Uprate (EPU)                      Core Flow 0 to < 30.9 %                                       < 0.33Wd+53.7%
Reference 6.16.                   Core Flow 30.9 to < 66.7 %                                    < 1.07Wd+30.8%
Core Flow 66.7 to < 99 %                                      < 0.55Wd+65.5%
Core Flow> 99%                                                Maximum of 120%
APRM High Flux Scram (Single Loop Ops)
Core Flow0to<39.1 %                                           <0.33Wd+51.1%
Core Flow 39.1 to < 61.7 %                                    < 1.07Wd+22.2%
Core Flow 61.7 to < 119.4 %                                   < 0.55Wd+54.3%
Core Flow >119.4                                              Maximum of 120%
Assumption 2.3.13                 APRM High Flux Scram (Reduced)                                <15 % Power 3.2    Environmental Conditions The following table identifies the limiting environmental conditions expected for each loop instrument.
Table 4: Environmental Input Data Basis             l Description                                                            lData Ref. 6.1,           Normal Drywell Temperature (Below 270 fi)                                 160 0F Table 2             Normal Reactor Building Temperature (Occupied Area)                       106 0F Ref. 6.5            Normal Radiation                                                         N/A (Assumption 2.2.6)
Ref 6.6             Accident Radiation                                                       N/A (Assumption 2.2.6) 3.3     Primary Elements ND-2-1-104 Data Table 5: Primary Element Input Data Basis                l Description                                                      Data Ref. 6.2               Maximum Temperature                                              600 0F Ref. 6.3               Nominal Operating Neutron Flux                                   1.2x1012 to 2.8x1014 nv Maximum Operating Gamma Flux                                     1.2xlO9R/hr Accuracy (PLEANSeTx Vermont Yankee Design Engineering                                                                                Page 14 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                    VYC-693A, Revision 2 3.4    LPRM Data
______________                     Table 6: LPRMIlnput Data Basis                 Description                   Data Ref. 6.2              Accuracy                      +/-0.8% CS Drift                         +/-0.8% CSI700 hrs 3.5    APRM A, B, C, D, E, F, Data Table 7: APRM Input Data Basis               j Description                   Data Ref. 6.11             Averaging Circuitry Accuracy                  +/-0.80% CS Drift                     +/-0.5% CS/2 weeks Ref 633               Trip Circuits (Reduced Scram)
Analyzed Drift           +/-0.5%CS/ 3 months (13 weeks)
Ref. 6.11             Trip Circuits (FlowBiased)    +/-1.0% CS (0 to 100% flow) 25A5903 Rev. I             Accuracy and Drift        valid for 36 months. Timing error not used.
(Assumption 2.2.19)
Ref 6.7               Calibration Interval:
Table 4.1.2 & 4.1.1   APRM High Flux Scram Trips    3 months (13 weeks)
LPRM                          2000MWDIT Reactor Heat Balance          Weekly 3.6    Flow Bias Error Data The following information is copied or extrapolated from VYC-690 Rev. 2. The accuracy associated with the cardinal flow rates for ARTS/MELLLA and EPU are used in the spreadsheet as an additional error associated with calculation of the APRM setpoints. Errors in VYC-0690 (as listed below) have been calculated based on an assumed maximum total recirculation span of 83,600 gpm (41,800 gpm per loop) to ensure maximum accuracy for recirculation flow indication in the control room.
However, the calculation of flow bias for the APRMs is based on an ideal flow of 65,000 gpm (32,500gpm per loop). Therefore to compensate for the difference in reference values for the errors associated with the flow bias a multiplier of 1.286 is used. As discussed in Section 2.2.7, the input into the FCTR is then scaled, during the core flow to recirculation flow verification, to 125% of recirculation flow. This multiplication has been performed in the spreadsheets that perform the detailed calculations for this document. The error is also multiplied by the specific flow correction value (i.e. if the flow formula is 0.33Wd+53.7 EPU 0-39.1% flow, then the random flow error would be multiplied by 0.33) in this same step.
Vermont Yankee Design Engineering                                                        Page 15 of 29

. ..     . ..  . . ..          : .. :  . ..     . ..... , .:     '.'. , . 11: ..,. .- .. :  . .. -              . . . ..
                                                                                                   . .    ..             . .       . I .. ... . 11.!-:-....:. . : :- ..
APRM/RBM Neutron Monitoring Trip Loops                                                                           VYC-693A, Revision 2      -
Table 8: Flow Input Errors Two Recirculation Pumps Running
                        % Core Flow         Random Error [%Calibrated Span]                Bias Error [%Calibrated Span]
20                                0.7266                                  0.4501 30.9                               0.5941                                  0.2937 31.1                               0.5927                                  0.2919 39.1                               0.5513                                  0.2327 54                                0.5143                                  0.1688 66.7                               0.4994                                  0.1367 75                                0.4934                                  0.1216 83                                0.4891                                  0.1099 99                                0.4834                                  0.0922__
119.4                               0.4791                                  0.0764 Table 9: Flow Input Errors One Recirculation Pump Running
                       % Core Flow Random Error [% Calibrated Span]                      Bias Error [% Calibrated Span]
20                                0.4673                                    0.1137 37.5                               0.4358                                    0.0608 39.1*                              0.434776                                0.058368 40                                0.4342                                    0.057 60                                0.4277                                    0.038 61.7                               0.427428                                  0.03698 61.9*                              0.427396                                  0.03686 62.5                               0.4273                                    0.0365
* Values linearly interpolated from VYC-0690 Ref. 6.27 4      CALCULATION DETAIL The detailed calculations of the APRM loop uncertainties, setpoints, testing tolerances, and margins have been performed using Microsoft Excel spreadsheets and are documented as Attachment B.
5     RESULTS AND CONCLUSIONS 5.1       Allowable Value The Allowable Value for each required point has been determined and the results are presented in the table below. Since this is a major revision of the method and calculation of Allowable Values and Setpoints no comparison to existing values has been performed.
Vermont Yankee Design Engineering                                                                            Page 16 of 29 I
I

APRMJIBM Neutron Monitoring Trip Loops                                                     VYC-693A, Revision 2 Table 10: Allowable Values Output Instrument                                          % RxP          mV           Curve % RxP APRM A, B, C, D, E, F Scram Trips ARTS/NIELLLA Flow Biased APRM High Flux Scram (Two Loop Ops)
Core Flow 0 to <31.1 % (point based on 25% flow)            71.1         5.688       <0.4Wd+61.10%
Core Flow 31.1 to <54.0 % (point based onO50% flow)          97.3        7.785      < 1.28Wd+33.31%
Core Flow 54.0 to <75 % (point based on 70% flow)           113.5        9.078      < 0.66Wd+67.28%
Core Flow > 75%                                            117.0        9.357              N/A APRMI High Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)             68.1        5.447       < 0.4Wd+58.09%
Core Flow 39.1 to <61.9 % (point based on 50% flow)          87.6        7.005      < 1.28Wd+23.56%
Core Flow 61.9 to <83.0 % (point based on 70% flow)         108.3        8.664      < 0.66Wd+62.10%
Core Flow> 83.0%                                           117.0        9.357              N/A EPU flow Biased APRM tHigh Flux Scram (Two Loop Ops)
Core Flow 0 to <30.9 % (point based on 25% flow)             58.7        4.696       < 0.33Wd+50.45%
Fore Flow 30.9 to <66.7 % (point based on 50% flow)          80.7        6.458       < 1.07Wd+27.23%
Core Flow 66.7 to <99.0 % (point based on 75% flow)         103.6        8.287       < 0.55Wd+62.34%
Core Flow> 99.0%                                           117.0        9.357               N/A
[APRMI High Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)             56.3        4.500       < 0.33Wd+48.00%
Core Flow 39.1 to <61.7 % (point based on 50% flow)          72.5        5.801       < 1.07Wd+19.01%
Core Flow 61.7 to <119.4 % (point based on 75% flow)         92.5        7.398       < 0.55NVd+5122%
CoreFlow> 119.4%                                            117.0        9.357               N/A Note: % CS is calculated based on multiplying the calculated Vdc terms in attachments 7.2 by 10 (100% Span/ lOVdc).
5.2    Setpoint Evaluation Results are presented below for the Limiting Setpoint (LSp).
Table 11: APRM Fixed Scram (Reduced) Trip Setpoint Results Description ITS: Analytical Limit (AL);        S 15.0 CTS: Tech. Spec. Limit (TS)
Limiting Setpoint (LSp)            11.72 ITS: Allowable Value (AV)          12.97 Margin to LSp (M1 )                +0.345 Existing Setpoint                  11.375 New Setpoint                       N/A Margin to Normal Operations       There is no stable operating point when the reactor is in the "Startu "mode.
These results are presented graphically in Figure 1.
Vermont Yankee Design Engineering                                                        Page 17 of 29

                                                  .. . ..  - " ...... : -', " : , '!, ' . . .. ..    . .- .,'.   , -. 7   .. - -' -' "  : :.,. . . .     :.. . . .
APRM/RBM Neutron Monitoring Trip Loops                                                                            VYC-693A, Revision Table 12: Limiting Setpoints and Calibration Cardinal Points Output Instrument                                                  % RiP                 mV           Curve % RxP kPRM A, B, C, D, E, F Scram Trips ARTSINIELLLA Flow Biased NPRNI High Flux Scram (Two Loop Ops)                                _
:ore Flow 0 to <31.1 % (point based on 25% flow)                            69.9            5.588          <0.4Wd+59.85%
Core Flow 31.1 to <54.0 % (pointbased on 50 % flow)                         96.1            7.685         < 1.28Wd+32.06%
Core Flow 54.0 to <75 % (point based on 70% flow)                         112.2             8.978         < 0.66Wd+66.03%
Core Flow> 75%                                                           115.7             9.257                    N/A APRMI High Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)                            66.8            5.347          < 0.4Wd+56.84%
Core Flow 39.1 to <61.9 % (point based on 50% flow)                         86.3            6.905          < 1.28Wd+22.3 1%
Core Flow 61.9 to <83.0 % (point based on 70% flow)                       107.1             8.564          < 0.66Wd+60.85%
Core Flow > 83.0%                                                        115.7             9.257                     N/A EPU Flow Biased MPRAIHigh Flux Scram (Two Loop Ops)
              -ore Flow 0 to <30.9 % (point based on 25% flow)                            57.5            4.596          < 0.33Wd+49.20%
Core Flow 30.9 to <66.7 % (point based on 50% flow)                         79.5            6.358          < 1.07Wd+25.98%
Core Flow 66.7 to <99.0 % (point based on 75% flow)                       102.3             8.187          < 0.55Wd+61.09%
Core Flow > 99.0%                                                         115.7            9.257                     N/A AIPRM High Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)                            55.0            4.400          < 0.33Wd+46.75%
Core Flow 39.1 to <61.7 % (point based on 50% flow)                         71.3            5.701          < 1.07Wd+17.76%
Core Flow 61.7 to <1 19.4 % (point based on 75% flow)                       91.2            7.298          < 0.55Wd+49.97%
Core Flow> 119.4%                                                          115.7            9.257                     N/A Note: Due to the small difference between As-Left and As-Found allowances,                               rounding of setpoints is not recommnended.
5.3      Calibration and Test Results Test As-Found tolerances (FI) and As-Left tolerances (C'T) are for the Fixed Scram (Clamp and Reduced settings) are defined in Tables 13 and 14.
Table 13: Calibration Tolerances As Left (CT)
Description                                                            LimitsVdc               Limits % RP APRMI Fixed Scram (Reduced) Trip                                        0.04 Vdc               0.5 % RP Table 14: Calibration Tolerances As Found (FI)
Description                                                            l Limits Vdc          l Limits % RP APRM Fixed Scram (Reduced) Trip                                           0.1 Vdc                1.25%
Vermont Yankee Design Engineering                                                                               Page 18 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                            VYC-693A, Revision 2-Table 15: Calibration Points, As-Left and As-Found Output Instrument                                      Setting   As-Left As-Left As-Found s-Found Idc    Min        Max        Min         pfax 4PRM A, B, C, D, E, F Scram Trips ARTSIMELLLA Flow Biased                                   _                                l HP.Migh Flux Scram (Two Loop Ops)                         _                                l ore Flow 0 to < 31.1 % (point based on 25% flow)          5.588     5.538       5.638     5.488           5.68 ore Flow 31.1 to <54.0 % (point based on 50 % flow)       7.685     7.635       7.735     7.585           7.78 ore Flow 54.0 to <75 % (point based on 70% flow)          8.978     8.928       9.028     8.878           9.07 Core Flow> 75%                                             9.257     9.2071      9.307     9.157           9.35 APR1I 1ligh Flux Scram (Single Loop Ops)                          _                    _      _          _
Core Flow 0 to <39.1 % (point based on 25% flow)           5.347     5.297       5.397     5.247           5.44 Core Flow 39.1 to <61.9 % (point based on 50% flow)        6.90      6.855       6.955     6.805           7.00' Core Flow 61.9 to <83.0 % (point based on 70% flow)        8.564     8.514       8.614     8.464           8.664 Core Flow > 83.0%                                          9.257     9.207       9.307     9.157           9.357 EPU Flow Biased
            %.PRM H1igh Flux Scram (Two Loop Ops)                                         _
            )w 0 to <30.9 % (point based on 25% flow)                  4.596     4.546       4.646     4.496           4.69 Core Flow 30.9 to <66.7 % (point based on 50% flow)        6.35      6.308       6.408     6.258           6.45 Core Flow 66.7 to <99.0 % (point based on 75% flow)        8.187     8.137       8.237     8.087           8.28 Core Flow> 99.0%                                           9.25      9.207       9.307     9.157           9.357 APRM High Flux Scram (Single Loop Ops)                                      .
ore Flow 0 to <39.1 % (point based on 25% flow)           4.400 4.350           4.450     4.300           4.500 ore Flow 39.1 to <61.7 % (point based on 50% flow)        5.701 5.651           5.751     5.601           5.801 Core Flow 61.7 to <1 19.4 % (point based on 75% flow)      7.298 7.248           7.348     7.198           7.398 Core Flow> 119.4%                                          9.257 9.207           9.30;     9.1557          9.357 Note: Recirculation drive flow input to APRM can be deternined by the equation RDF (Vdc) = % flow/125
* 10.
Table 16: Total Loop Uncertainty and Non-Test Error Output Instrument                                                   ILU % RxP        Son Test % RiP APRM A, B, C, D, E, F Scram Trips ARTS/MELLLA Flow Biased H.M High Flux Scram (Two Loop Ops)
Core Flow 0 to < 31.1 % (point based on 25% flow)                     -4.55%                      -3.303' ore Flow 31.1 to <54.0 % (point based on 50 % flow)                         -4.94%                      -3.69o/
ore Flow 54.0 to <75 % (point based on 70% flow)                             -4.47%                     -3.22o/
Core Flow > 75%                                                              -4.29%                      -30404 APR.I IHigh Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)                               -4.36%                      -3.11%
ore Flow 39.1 to <61.9 % (point based on 50% flow)                            -4.49%                     -3.24%
ore Flow 61.9 to <83.0 % (point based on 70% flow)                            -4.35%                      -3.103' Core Flow > 83.0%                                                              -4.29%                     -3.04o Vermont Yankee Design Engineering                                                               Page 19 of 29

APRM/RBM Neutron Monitoring Trip Loops                                                 VYC-693A, Revision 2 Table 16: Total Loop Uncertainty and Non-Test Error Output Instrument                                     iTLU        % RxP Non Test % RxP EPU Flow Biased PM High Flux Scram (Two Loop Ops)                                                 .
ore Flow 0 to <30.9 % (point based on 25% flow)                  -4.50%                 -3.25&deg;k   l ore Flow 30.9 to <66.7 % (point based on 50% flow)               -4.82%                 -3.57Th ore Flow 66.7 to <99.0 % (point based on 75% flow)               -4.41%                 -3.16l Core Flow > 99.0%                                                 -4.29%                 -3.04ol PM High Flux Scram (Single Loop Ops) ore Flow 0 to <39.1 % (point based on 25% flow)                    -4.35%                 -3.10%l ore Flow 39.1 to <61.7 % (point based on 50% flow)                  .4.44%                -3.190/
re Flow 61.7 to <1 19.4 % (point based on 75% flow)              -4.33%                 -3.08%
ore Flow> 119.4%                                                   -4.29%                 -3.04%
Table 17: Total Loop Uncertainty and Non-Test Error Putput Instrument                                            TLU %CS         Non Test % CS lPRM A, B, C, D, E, F Scram Trips                                       .
ARTSIMELLLA Flow Biased High Flux Scram (Two Loop Ops)                                                                    l Core Flow 0 to < 31.1 % (point based on 25% flow)        -3.64%                 -2.64%
Core Flow 31.1 to <54.0 % (point based on 50 % flow)             -3.95%                 -2.95o/
Core Flow 54.0 to <75 % (point based on 70% flow)                -3.58%                  -2.58o/
Core Flow > 75%                                                  -3.43%                  -2.43o/
PRM High Flux Scram (Single Loop Ops) ore Flow 0 to 539.1 % (point based on 25% flow)                -3.49%                  -2.49Y ore Flow 39.1 to <61.9 % (point based on 50% flow)             -3.59%                  -2.59o/
ore Flow 61.9 to <83.0 % (point based on 70% flow)             -3.48%                  -2.480/
Core Flow > 83.0%                                                -3.43%                  -2.43o/
EPU Flow Biased PM High Flux Scram (Two Loop Ops)                    .
ore Flow 0 to <30.9 % (point based on 25% flow)                -3.60%                  -2.60&deg;/
ore Flow 30.9 to <66.7 % (point based on 50% flow)             -3.85%                  -2.85o/
ore Flow 66.7 to _99.0 % (point based on 75% flow)              -3.53%                 -2.53Y Core Flow > 99.0%                                                 -3.43%                 -2.43/
High Flux Scram (Single Loop Ops)
HP
              -ore Flow 0 to <39.1 % (point based on 25% flow)                -3.48%                  -2.48/
Wore Flow 39.1 to <61.7 % (point based on 50% flow)              -3.56%                  -2.56o/
Wore Flow 61.7 to <119A % (point based on 75% flow)              -3.47%1                 -2.47o/
sore Flow> 119.4%                                                -3.43%                  -2.43o/
5.4     Calculation Review and Impact Consideration 5.4.1    This calculation evaluates the uncertainty of loop components for design changes including Extended Power Uprate. The uncertainty determined by this calculation Vermont Yankee Design Engineering                                                     Page 20 of 29

APRM/RBM Neutron Monitoring Trip Loops                                               VYC-693A, Revision 2 will be used as input for the Reactor Scram Flow Biased and the APRM Fixed Scram (Reduced) Trip Setpoint and Allowable Value results.
5.4.2   The Design Input Considerations of ARTS/MELLLA and the VY Extended Power Uprate as well as the change in the methodology used to develop Limiting Sctpoints and Allowable Values have been considered in this calculation. The setpoints developed in this calculation are not applicable until the VY licensing amendments BVY 03-80 for Extended Power Uprate and BVY 03-23 ARTS/MELLLA are approved (as applicable).
5.4.3 The function of the instruments covered by this calculation is an assumed input in the Reload Licensing Analysis. This analysis does not assess conformance to 10 CFR 50.46, "Acceptance Criteria for ECCS for Light Water Nuclear Power Reactors," and Appendix K, "ECCS Evaluation Models". The results of this calculation do not identify errors or require changes to the Reload Licensing Analysis. Therefore, the reporting requirements of 10 CFR 50.46 are not applicable.
5.4.4   A review of the Vermont Yankee Event Report Database was conducted to identify any Event Reports that would impact this calculation. This review identified no event reports, associated with these components.
5.4.5 Precursor calculations used for design input to this calculation are not impacted by the results of this calculation. Any applicable interactions due to changes in precursor calculations will be addressed per AP 0017 during the change process for those calculations. Calculation VYC-0690 [Ref. 6.27) provides direct input to the flow errors used for this calculation.
5.5   Summary of Requirements 5.5.1  The current calibration procedure, OP 4308, Rev. 21 [Ref 6.25] requires update to accurately reflect the LSp and As-Found and As-Left tolerances. A precaution should be added to Ref. 6.25 to ensure that M&TE with an accuracy better than 0.05% of span is used to set the flow bias input value during calibration.
5.5.2 This calculation is not an implementing document and a 50.59 screen or evaluation is not required. The output of this calculation is implemented through update to applicable plant documents (i.e., OP 4308, FSAR). The downstream process that updates applicable output documents will satisfy the 50.59 evaluation requirements.
5.6   Summary of Recommendations 5.6.1  Based on the results of this calculation the following changes should be made to the evaluated trip setpoints:
5.6.1.1 APRM Flow Biased Scram Trip Setpoint.
Vermont Yankee Design Engineering                                                  Page 21 of 29

                               . . . .. .. :. ,. ~:- , ". : ' . :: .: ! : ' : , :' : ': ' .' . - ." ' ' ,,                    . .... .
1:1.1.1".:. 1 :-"ZI~~~.
APRM/RBM Neutron Monitoring Trip Loops                                                     VYC-693A, Revision 2 5.6.1.1.1  The formula to develop the curve for the APRM Flow Biased Scram Trip setpoints must be changed in accordance with Table 12 for the specific application of ARTS/MELLA or Extended Power Uprate.
5.6.1.1.2  Revise the As-Left and As-Found tolerances as defined in Table 15 for the new calibration points.
5.6.1.2 APRM Fixed Scram (Reduced).
5.6.1.2.1 Trip setpoints must be changed in accordance with Table 12. The values for Allowable Value and Limiting Setpoint do not change for this function for ARTS/MELLLA or EPU.
5.6.1.2.2 Revise the As-Left and As-Found tolerances as defined in Table 15 for the new calibration points.
Vermont Yankee Design Engineering                                                         Page 22 of 29

.14 I .   .. ..  -  -   . .. 1 ; : ." -, - , - , - _- .:    .: :
                                                                                                                                                             , .. .- -: I"-
APRM/RBM Neutron Monitoring Trip Loops                                                                                            VYC-693A, Revision 2 CTS: Tech. Spec. Limit (TS)
ITS: Analytical Limit (AL) = S15% RP UXL                 Uumr ITS: As-Found (AV) = 12.97% RP Ut l                   It                     Limiting Setpoint (LSp) = 11.72% RP Margint Setpoint 11.375% RP
             <process>
I
                       - I-            I Normal Range of Operation Figure 1 APRM Fixed Scram (Reduced) Setpoint Vermont Yankee Design Engineering                                                                                            Page 23 of 29

                                 . .e .. .                                                              .
APRM/RBM Neutron Monitoring Trip Loops                                                   VYC-693A, Revision 2 A/M APRM FB SCRAM (TLO) 120 110 100 at 90 S..
   .E 80 0
10.0 Cn 70 60 50 40 0     10        20           30     40        50       60      70     80       90       100 Drive Flow I --- Scram Analytical Limit       --aScram Allowable Value     .--- Scram Nominal Trip Setpoint I Figure 2 APRI Flow Bias Scram Analytical Limit, Allowable Value, Nominal Trip Setpoint (ARTS/IMELLLA) Two Recirculation Loops Vermont Yankee Design Engineering                                                       Page 24 of 29 t

. . . .  .  . . . ..   . .... ....            "- . ,             , .. . . .. .  . : ::. : -- : .-. ::   :, .". .... - ,  :,. -4 APRM/RBM Neutron Monitoring Trip Loops                                                           VYC-693A, Revision 2 A/M APRM FB SCRAM (SLO) 120 110 100 D.y 90 n-so
         .E 80 0
0 Cn 70 I.
60 50 40 0             10 20     30       40       50         60           70         80        90          100 Drive Flow
                  -*-Scram Analytical Limit  -4.-Scram Allowable Value         -u-Scram Nominal Trip Setpoint I Figure 3 APRN1 Flow Bias Scram Analytical Limit, Allowable Value, Nominal Trip Setpoint (ARTSAIELLLA) One Recirculation Loop Vermont Yankee Design Engineering                                                               Page 25 of 29

. I. .             ..  .. .               . . .... . . .                                                        ..   ... ... :
APRM/RBM Neutron Monitoring Trip Loops                                                  VYC-693A, Revision 2 EPU APRM FB SCRAM (TLO) 120 110 100 z-   90 0-g
          .S- 80 0
0 4-
          'O 70 50 60 50 40 0        10      20       30          40      50   60       70        80       90       100 Drive Flow Sccram Analytical Limit   -+-ScramAllowable Value        -a-Scram Nominal Trip Setpoint w
Figure 4 APRM Flow Bias Scram Analytical Limit, Allowable Value, Nominal Trip Setpoint (EPLJ) Two Recirculation Loops Vermont Yankee Design Engineering                                                      Page 26 of 29

                                                               ... ... ..:.: .4:. .:.   . ..:,:            :  .- ~~~~~~~~~~~~~~~~~~
APRM/RBM Neutron Monitoring Trip Loops                                                             VYC-693A, Revision 2 EPU APRM 1B SCRAM (SLO) 120                          l     I i         I I l
110 100
: a. 90
   .E 80 0
40.
U0 70 60 0
50 I
40 I                                                              I           .          I       I 0     10      20      30     40   50     60 70             80         90            100    110      120 Drive Flow
        --   Scram Analytical Limit   .- Scram Allowable Value     -u-Scram Nominal Trip Setpoint Figure 5 APRM Flow Bias Scram Analytical Limit, Allowable Value, Nominal Trip Setpoint (EPU) One Recirculation Loop Vermont Yankee Design Engineering                                                                 Page 27 of 29

APRM/RBM Neutron Monitoring Trip Loops                                         VYC-693A, Revision 2 6      REFERENCES 6.1  "Instrument Uncertainty and Setpoints Design Guide," Vermont Yankee, Rev. 1.
6.2  Design Specification 22A1366, Rev. 3, "Neutron Monitoring System" 6.3  Design Specification - Data Sheet 22A1366AF, Rev. 1, "Neutron Monitoring System" 6.4  "Vermont Yankee Updated Final Safety Analysis Report, Rev.17."
6.5  "Vermont Yankee Environmental Qualification Program Manual," Rev. 38.
6.6  "Vermont Yankee Design Basis Radiation Dose Specification," Yankee Nuclear Services Calculation VYC-193. Rev. 4 6.7  Vermont Yankee Technical Specifications through Amendment 212.
6.8  Not Used 6.9  AP-0017 Calculations and Analyses Rev. 8 LPC 2.
6.10 Not Used 6.11 Design and Performance Specification 175A1259, Rev. 1, "APRM".
6.12 Not Used.
6.13 General Electric Instrument Setpoint Methodology, NEDC-31336 (GE Proprietary), October 1986, Section 3.19 and 4.5.
6.14 NEDE-2401 1-P-A-14, June 2000, General Electric Standard Application for Reactor Fuel (GESTAR II).
6.15 GE-NE-0000-0012-0531-01-01 Revision 2 November 2003 Project Task Report "EntergyNuclear Operations Incorporated Vermont Yankee Nuclear Power Station ARTS/MELLLA" Task T0506:
NSSS TS Instrument Setpoints.
6.16 GE-NE-0000-0016-5688-01 Revision 0 August 2003 Project Task Report "Entergy Nuclear Operations Incorporated Vermont Yankee Nuclear Power Station Extended Power Uprate" Task T0506: NSSS TS Instrument Setpoints.
6.17 GE Performance Specification 25A5903 Rev. 1, "Flow Control Trip Reference (FCTR) Card".
6.18 EMPAC Database.
6.19 Core Operating Limit Report (COLR).
6.20 Measuring & Testing Equipment Uncertainty Calculation, VYC-1758 Rev. 0.
6.21 Not Used.
6.22 Not Used 6.23 OP-43 108 Rev. 6, APRM Functional/Calibration (RMSS not in run).
6.24 OP-4400, Rev 21, Calibration of APRM System to Core Thermal Power.
6.25 OP 4308 Rev. 21 APRM Monitor Calibration.
6.26 OP-2429 Rev. 14 "Recirculation Flow System Baseline Data Collection and Instrument Calibration."
6.27 VYC-690 Rev. 2 "Recirculation Flow Loop Uncertainties to APRM".
6.28 NEDE-2401 I-P-A-14, June 2000, General Electric Standard Application for Reactor Fuel (GESTAR II).
6.29 NEDC-33089P, "Vermont Yankee Nuclear Power Station APRM/RBM/Technical Specifications Maximum Extended Load Line Limit Analysis (ARTS/MELLLA)," March 2003.
6.30 NEDC-33090P, Rev. 0, "Safety Analysis Report for Vermont Yankee Nuclear Power Station Constant Pressure Power Uprate," September 2003 6.31 BVY 03-23 March 20,2003, Technical Specification Proposed Change No. 257 Implementation of ARTS/MELLLA at VY Vermont Yankee Design Engineering                                            Page 28 of 29

APRMJRBM Neutron Monitoring Trip Loops                                          VYC-693A, Revision 2 6.32 BVY 03-80 September 10, 2003, Technical Specification Proposed Change No. 263 Extended Power Uprate.
6.33 VYC-2252, Rev. 0 "Drift Calculation for Average Power Range Monitors."
7     ATTACHMENTS 7.1  Loop Diagram [ 1 pg]
7.2  Calculation Detail (BI through B4)   [8 pgs]
7.3  Design Specification 22A1366, Rev. 3, "Neutron Monitoring System"        [2 pgs]
7.4  Design Specification - Data Sheet 22A1366AF, Rev. 1, "Neutron Monitoring System"[1 pg]
7.5  Design and Performance Specification 175A1259, Rev. 1, "APRM" [3 pgs]
7.6  GE Performance Specification 25A5903 Rev. 1, "Flow Control Trip Reference (FCTR) Card
[ 23 pg]
7.7  AP-0017 Forms and Interdepartmental Review Form [7 pgs]
Vermont Yankee Design Engineering                                             Page 29 of 29 Zs

LPRM/APRM NEUTRO' MONITORING (APRM LOOPS)
REACTOR INDICATOR I  DETECTOR (TYPICAL OF 40 PER LOOP)
ALARM CIRCUIT I
(UPSCALE & DOWNSCALE LEVEL)
ALARM CIRCUIT (UPSCALE
                                                                           & DOWNSCALE LEVEL)
SCRAM CIRCUIT (UPSCALE LEVEL)
DW -         -RB-CR ALARM CIRCUIT (UPSCALE LEVEL &
COMPARATOR)
L.      .      l              lRECWRCULATION FLOW ALARM CIRCUIT                        l  (REFER TO VYC-690)
(UPSCALE& DOWNSCALE LEVEL)                       __                   I CD qA o6  -
To  C., 5 VYC-693A

APRMSCRAM       TRIPPOW REVEW                                                                                                 ARTSM4EUA   TwoLoop                                                                                                          WC-0693A,  Resion 2 Abdsnei 7.282. Pgs I of2 A                                     BC                                                     0                                  E                                   F              I                                                                   11 I APRMSamsCialculnbARTSiMEULLA TwoReendisi L- OVSImm                                                                                                                                             a     01uswdor054    a6 2                                                        ~~~~~~~~~~~~~~~~~~~~~SPAN SpotkpAnb                                                Lknf*                     SENSIfhOTY                      ACCURWACY                                        REPEATABUJTY 3EOUPMIENTLto.                         INSTRUMVENTTYPE                       %                                                   Foiorst rAPort %    RP                                                        %CSC 4                                                                                                                                      O.W022453.7 ND1402-i-104LPRMDETECTOR 7                     .LPRM                                                 __   _  _    _ _  _   _     _   _  _  _  _  _   _   _  _  _  _    _  _  _  _  _     _   _  _   _    _   _ _  _  _ _0.26              7%
S                     APRM                                                                               __  _ _ _ _  __ _ _ _   _ __ _ _    _ _ __  _ _ _                                                  .000%
101                     FLOW SOCA               03.%125                                                  0.40                               72.40                                                           2.0000%
III                     FLOW   BIASEDOSCRAM   (31.12-540%)                      22                       120                                76.81                                                           1.0000%                             _       __________
12                      FL   WBLASEDSCRAM(540.75.0%)                            125                      0.80                              10614                                                            I.0000%           _   _ _ _   _ _   _   _ _ _   _    _   _ _  _ _ _   _   _ _ _  _  _ _   _
1.3                     FLOWBIASEDSCPAM(,75.0%)                                                       rmnisV i2               ~                  120.00                                                           I.D_______DD100%
14                      FO(ED  SCRAM   (REDUCED)                                125                       Ws,                               1i.0                                                            1.000%
15                                                                                                      % CS__                                                    _ _ _ _ _ _ _ _ _ _ _ _     __                                _ _ _ _ _ _      _ _ _ _ _ _ _ _        _ _ _ _ _ _ _ _ _      _   _ _
16CALIBRATION    EQ.U'MENT      UN4CERTAINTY  (MarE)                                                   0071%                (2.3.12INTEXT 17 RLOWINPUTUNCERTrAN1BIAS            (FROMVC.9000REV.2)                                                0.4501                             0.2919                             0.100                  ________
10 R.OWW&#xb6;JTUNCERTASOMYRAND0OM(FROMVYC*000.                 REV.2)                      L___            0.7206                              0.5927                             0.5143               CSFORFLOWSIONAIS 128.6%
19 FLOW UNCERTAtM 00smEFFECT             (%RxPOWER)                                                  0.2315%                              0.4805%                            0.1433%--             CSFORPOWER     IS 125%       _     _______________
20 FLOWUNCEfRTANI        M IJOMEFFECT               .0es.25%$TSe~Sc23.q(%R POWER)                    0.3953%                              1.0500                             0.4054%
21 FLOWSEITTWTOLERW4CE                                                              0.25 (SORT( I0"2C2M~200 l28~l0 (SORTE18-2.$C$2lA2)            00 .28W011 (SORT(FIB'2.$C$21'2 i00r1.286&#xb6;DI2 22 MM"h FLOWVALUES             TOBEEVALUATED RFOW)                                                         20                                31A 22 FLOWVALUES      TOBEEVALUATED        I%FLOW)                                                      20-31.1%                            31.1-540%                          54.0-75.0%
24 M!EUM
        ,       NMAER OFLPRW        sPERAPRM                                      0                                                                                                                                              _   _  _   _  _    _  _   _   _    _   _  _ _   _    _  _  _  _   _  _
25 FRlMARY     ELEMENTACCURACY       (%RP)Ss~i250.02%                                                    Bins     ~      A               0.340000%
20 ROCE   55    MUN           ACRACY%         )       i2.6.)               2320%                                            _     _______                                                          _______
28 TECH    SPECLUN.r REOLMED       FORCTS                                     120.00 %RP 20 AO4ALYTICLUMT    REOUIREDFOR       RS                                      120.00 %RP 31 CSw4slRwswsom                                       ci           .5SS                                                                                           ofCsiobrsmoTwsns% RP            sIOssofca~x00oTrms        N     ESTW UNERTAWI 32 RLOWBIASEDSCRAM(20-31.1%A                                                                                                             E3%IC$10                  LOOP TESTING    UNJCERTAINTY LOOPTESTINGUNJCERTAINTY      0.O4SOT 5E92P24$C$2246-20'm2401194N510) 35CLIANEFFC(CE)                                                               CALIBRATION TOLERANCE              CALIBRATIONTOLERANCE                        $C$I0lSORT(A3W~)                    SORTIA35?2)       OB.B'SORT   $E$25124$CS2B'$2.ES2'24OS194$NSI6          -5C$2540019 34          %CS      I%RP                                                                                                                   15CS                               %RP                             %CS                                                 %RP 351       1.0000% 10.625                                                                                                                   0.50%                                t.25                          1.00%                                              2.2440%
301       .1.00%      1.0.625                                                                                                              .0.50%      ___                       1.25                        .1.00%                                               32956%
381         -A35 40 FLOWBLASED     SCRAl (31.1.540%)
41 CALIBRATION4  EFFECTMCALEBRATIORTOLERANCE                                                                               CALIBRATION  TOLERANCE                  LOOP TESTING    UNICERTAINTY LOOP    TESTING              NONTESTING UPICERTADITY             ERROR 42          %CS                                                                                         %RP                                  5CS                              -%RP                             %CS                                                 %RP 43        1.0000%                                                                                       0.625                              0.50%                                1.25                          1.00                                               2.3909%
44        l.1.000%                                                                                     40.625                             4050%                                -1.25                         .1.00%                                             .3.6914%
45 46 41 FLOWBASEDSCRAM           (54.0 -75.0%)                                               CALIBRATION 48 CAUBRATI0PN   EFFECT    (CE                                              ____        TOLERANCE                            ____________                          LOOPTESTING     UINCERTA*TM     LOOP TESTESUN*CERTAtN1    NOTESTING ERROR 491         %CS       I                                                                                 %RP                                 %CS                                %RP                              CS%RP 50        1.0000                                                                                        0.625                              0.50%                                2.2                           120%32595%
SI       -1.8000%                                                                                       -0.625                             -0.50%                              .1.25                         .200                                                 3.2197%
53 54 FLOW    BIASE0 SCRAMJ    i-75.0%)                                                    CALIBRATION 55 CALIBRATICONFFC          ME                                                           TOLERANCE                                                                 LOOP TESTING    LUN0ERTAFMT LOOP     TESTINGLESCERTAINTY  NONTESTMSERROR 56          %CS2      I      ____________                                                                %RP                                %CS                                %RP                             %CS                                                 %RP 57        100%0.50                                                                                                                         0.40%                                2.2                           1.00%                                              2.2193%
a0       -1000                                                                                           -050                             4040%                                -1.25                         -1.00%                                              -3.0303 00 FIXED   SCRAM  (EDUCED)                                                              CALIBRATION 61 CALIBR.ATIN   EFFCT C                                                                TOLERANCE RPLOOP                                                                TESTING    UKIERTAINTY     LOOPTESTS LUNCERTAINTY    NONTESTING    ERROR
.6           %C05                                                                                                                            %CPS0                              %RP                             %C05                                                %RP 03        2.0000%                                                                                        0.50                              0.40%                                1.25                           1.00%                                             2.2193%
1641      -1.0000% _______________-0.50                                                                                                     -0,40%                               -1.25                         -1.00%                                             -3.0393%
693AU2ARTSMELULATswoLo            Owpna" k       l pd~sk6entd*

APRPMSC TRIP   PONTREVIEW                                                                                           ARTSMtELLAT*wo   Loop                                                                                                      WCVYM9AlPevir. 2 Aftorol 7.2B2.
lPm   t 2
_                I      I      l            J                             I           L     [            I            N                   0                   P                  0                 R                  S                          I I ekmim bisevidranlomr erom                                                                                                INSTRUMENTS              IAV =AL . SQRT(SES25A2+SC$26o2+$DS2O,24$O$19+SOSO).$CS25-$DSl9 2              ORIFT                  IJ4EARIJY               WTSTERESS         ENVtROtEFE. SEIShC                 SlbtS SOUARMIW(4)
                        %            J  Ic         %CS C28 Pr-of, e.,uow otAtcuroy P dom t orn_ reot dRP oo                                                      D20:FlowUnertloltyRamdom E.ttlncdode 0.25%         STIn apren eoftRr POYER 0 2667%                                                                                            0.00ott01            00.001111                          0t9 Squaredeoimblnthoitoffiu0C                    tLPRlt.dAPlMCoovedpo fo dodtelrtoolfrm                              dtmetfP 8            0.5000%                                                                             000            0 00010000           000003906                          Ni6 Sqoured    eooblnsontof erosbs for .0 LPRM nd APRMmreglnglfren, Coverted topfreet RF  P.
000000000       Ij   0oaoo0 0        I tI i     1 ooooo toomo               _-
000015625 0.000t1525 t2            0 0000%                                                                                            0.0015062s           =.aoooo0 LSo =AV.CS10             l SORTIA35A121                   P                    +/-
lA3S:AcvurvuyorthA 35 Accurecyof theFCTR Card SU74NS    N9)    IsUAos 091           _                 I-16                                                                                                               I00011111            0.00005017 Swnote sqtwe nP. MMLPRUPmretaiit MidortwVW$ Sr"PS Plo)                          I 00o0oo070 CALRTO3N EQPMENTCO6NVERTEDTO%RPAN                     S0UAED E1C2               I I                I  ~(016/ooCIoA21                      I                    I              II 000005096 So ofto cirafboioerrorand One       drfltnd onrdrtreruorom.
S"016.017) 21 22 23         ._                                     _                                                        ITot LoopUrieoar4i 251 6-                                 t M ,ethod  IAV     I      _      0190041 AT     I   _ _.   ,. _                                                                              ,                 -1       -
32          L35iC010'100                 ITS:(Ay)                   LISP            SETP0ONT 33                                                                 %RP N35*G3m                                                                                                         %RP          T     %CS     I         VDC                        %RP 67.r5                           5.53                IVA                                     5.53              6910              5478%     I        S048                        6843 0354MtSIOfSM22)                                                                                    533                0oso             53.70%   1         5.38                        67.23 61.10                  59 85 39 ol  AV ard Selpert Cims_       0 4Wdr6l 10              O4tWdtS6              -5 401_1                                  MethodI AV        I LMATNSETPOI4TI                                           MAR1t4 41                                      ITns(AV)                   LSP 42 V.CS                                       RPP                                                                                                                                                                                                 %RP 57.99%          -  560                         7T49 33231                                                                                  I      5949%                 565      1        7062              56.9%    1          570                        71.24 12r"d33                  12rWdr32 0       -                                                                            I          I                                   i
_       _ _                  -         j       ~     I              -         I iORGO4 MedhdI A                                                         11          IWWGIN                      CT-S          TOLERANC      ()                I ITS:(AV]                                                 VALUE               (M7)                         _I
                                                  %RP           i         %  RP               Vdo         Vdc               %   RP 50            1.8052%                     10292                   10t.67              &13         B23                 WA 51            425758%                      67.28                  6603                                                                                                                                                                          10105 0 66WWd467.28            0 06Wdo0603 I~                 I                                    I-.
                                                                                                                                                                                                                    -               C 53 54                                                                                                                                                                                                                                  eITOLERANCE MethodI AV             m110 SETK)N0                      ALLOW                AARGN                      CTS      *lS-9*UNTOL.ERANCE (IT)                                            CA
                                                 -S.:IAV)                  LSp                           VALUE
             %CS                                  %RP                     %RP                 Vdo         Vdc               %RP                   9C5                 VDC               %RP                %CS             _VCC
                       &#xb6;7755%                     11S96                   11571               929         9.36                 NA                93.57% -        -93   35               11e.96            9Z97%_              9 30
_24315%                                     I _ _ __ _ __ _ __     -                          _ _ _ __-_ __-    __        91.57%     1                                              92.17%              9sn LUMSETP-OfSf 3-__IV_                            ALLIOABL             wAGIN                      CTSAS-FOUND      TOLERANCE  (Ft)                                            CA ITS:tAVI                  LSp                           VALUE
             %CS                                                                                                                                   %CS      l         VDC                90%
R               %CS     F         VOC
                                                                                                                                                 &#xb6;0,38%               10.4    1           1.97             9.78%    1       -0.98 8 39%                0.84      1        10.47             As -. I          on           i            11 11 R"113 RTS9EULLATwo LoopOprallon       oit updit1edforwAih 093At2A
' .t, ,
.1

APRUSCRAM   TRP POWREVIW                                                                                       ARTSMELLA    % tLp                                                                            VYC0403A   Rrvnmi2 Aflt.c..w 729B4. PaoI of2 A      I8                                            I           C          i            0          i                  E            l                F          I                             Cl I AP10M SorCa~         fmARTSWUL1A   Sivo~iekktiafi                                                                                                                        Vd*, busod onTaN..6s and7aIoowuy  aid A Iii_
3 Pi      700!PW                                                                                                      ACCURACY            REPEAIABITY EOW'INITI.a                  FRUETYKrPE                                                                                                                                                           %CS                    %CS
_PRU                                                                                                                                                                              o 2407%
I                  TPRMt                                                                                                                                                                            oM Mo~
                   ,TYPES' 10                                     39M 1%                                                   040                                                                                                  M M00 11                                     I .61 0%)                                                1.26                          7605                                                                  1.0000%
1t               IFLoOW SED   S otji(6g8830%)                            125                                                    -
FLOWOIAEDSCIRMN20%)                                                                                        12000o IsO,0 (213 t2INETEXT)
FLOWINPUTLUCERTAINTYAS    (FROM  VY-6K REV0.2)                                              0137                        0058360 FLOWWM UKcERTAINY              ~RCM RAND)OU VyC-49ILREY.2)-                                              04003                       04340770                                                     AIS 120 0%
FLOWUNHCERTAINTY BIASEFFECT (TOR5, POWER)                                                    *0505%                       00003%
FLOWUNCERTAJTY0  RMO20AEFFECT    x~nct~do25%    S..2.3 436%o POMER)
STC                                          112728%                      0 8250%                        0.4203%
FLOWSETTINGOTOLERANCE                                                          025 (ScTPD~r2C2I'2YI003-M"E0   SORT(E10'2.6C$21'Oyl Mrl.20r0  (SOT['18'2C%212Y1OO)
UINAAMd FLOW  VALLES  TOBEEVALLUATED (%  FLOM%                                                  20                                                         M.1.
FLOWVALUES 70089EVALUATED  6%  FLOM~                                                       20239.i%                   39.1.41690%                     010.83 0%
UMMMUNLU3EOFLPR~s       P14R APRU
-2                                                                      2 29%
TECHSPECLOOT REQUIRED  FORCTS                                        2000 MNAILYICLWTREOUIRED  FORITS                                         t2000 3RATEFONEFFECTCF                                                        TOLERANCE CALIBRATION
        %CS                                                             %Rp 1.0400%                                                          0 625 010        _____
40625
-3 IBRAT CAL   ONTOLERANCE                                                               LOOPTESTN0tUNCERTAMITY I       l        --       TEsRSTINERR(
                                                                        %RP                                                   %RP                            %CS.        I                            flRP           I       %CS 18600%
_                                                                                                                                                                                                                         *25930%
                                                                                                                                                                                                                             %CS I 7970t%
                                                                                                                                                                                                                          .244080%
                                                                                                                                                                                                                             %  CS t.7755%
24315%
                                                                                                                              .1 25                         .100 %                                  -30393%               I24315%
073A-B4  AMTS.EL S140iLoo"Ow~~nA-Weuliopd           - *~ngl

APIUtSCRA4TRIPPOPJTREVEW                                                                               NRl1tLSUAU*Swp                                                                                           VYC-0893k R.N.m 2 72BKPop.2of2 Affach-mt I        di   ;    I        j      I       K     I      L    I    No    I         N        I         0        1      P      I         0     I        R      I          S      I                      I I                                                   I     I     I
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                                                          %C         XCS
                                                                     %         I ACCURS             ILL OTHERS                    RonTestingF,, l:I (lGSM00iSC3IlI   Ii       00car 1 _
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                                                                                                                                                                   -- I 2 So 601A2_4 ARTSSlUA Sim Leop Opw#WAalyswol updettd 1'.dj

APRVOSCRAM  TRPPONTREVIEW                                                                           EPUTo Loop                                                                        VYc.Mt30R#.t 2 Adasnmoo 7.2Bl.Ps" t1of2 IA     IB                                        I          C     I                       0             E           I               F             i                         0G    r               0I tPltS     Ucdat    fo. Fotndd Pm t#tmt     o R.Wude L.. Omwioio                                                                                         IVou boo.anTahn 6 mWdianmrwd t 6                 cmS APRM
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to                rt0.EiASEDSt AU(205 0B%)                           125                                            70 II                RLOW M AS0
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Is _______________                      I 0%)                         12S            U_
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14                                                                   121                  we                    tSW0D 6000%
04501 (t72ftE 0 t10%
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21 lhVSEt4G rc tERAt4CE                                    l                                                                   (SORTTW.-SCS21 2Y100Yt27tt'11 066I                                                 .2       00 230 9%                  t359-6                      66.t7-00 6 PERtAPRU 27                 I 2S:tiF SPECltT ROOJIED       FORCTS 2n ANWLYTtC  LUT RE/IiRD FORITS                                       120.00_ % RlP SRSSd Cainmon Tg                                         . Cs LOOPTESTt9C   JN0ERTAtiTY SORTCA30*2)
                                                                                                                                              %CS                                              : CS___     __    -
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                                                                                                                                                                                                                 -Sl60
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                                                                                                                                              %CS 100%
                                                                     -04 2  -             050 -
                                                                                         .6                                                 .100%
LOOPTESTING0  LCERTANTY ;
                                                                                                                                               %CS%
                                                                                                                                            .100%
                                                                                                    -T  tOOPTI           55AtT      LOOPTESTtiG  tINCERTAINTY_r;
                                                                                                                %RP                           %CS 125 IE                                        - -     - 050
                                                                       -y       __  _    040%                    .1.25 PTESTS   ULNCERTAMP0
                                                                                                                %IRP 040%                     125
                                                                                        .040%                   .1.75 002A.B1EPtJTwoLoop        Af016,1updated bti           bmutib

APRRUSCRAU   TRIPPaSr REVEW                                                                                                       EPU Two.L.                                                                                    VYCe3IA Rllio 2 A12Btuci r 201.Pq. 2d2 I           I          Il      . I         K         I         L          I       U                 N           I          0              P       I       0       I      K      i       5
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                           =~     -tMARiTY  I    HYSTERESISlENVIROI EFF.I                SEISMIC
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7          0M207%                                                                                                                                 _   -    Ol0:SquaedtmIen-hi5 d0*TDRitud efto1lowtI IPRMendAPRlM Crd tePWd doRP 0.1000%                                                                                    o00a10000 I           0003NO4 I 9
POWER Q0525             I     00 o0e        I               I                I                         -4.
12          00000%                                                                                     0ooo01sm I            o~owoxoo      LSp*AV $C$10SRT(A35A2))                           -
13          0.000%                                                                                     C00015625 _T o.0 0no0
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V24 1200 1.00)0%
II            %CS 0 0C1%               (2312E1  XTI) 0 03698 FLOW  UNCERTANTY    F                                                                                                     as 21 FLOW    SETTNG  TaERANCE                                                        (SORTD168'2 C2Vy10yrl 286'010  I(SORT(E12-C$CS21   2Y106r125t'011  fSOFTf(Ie2o1CM21 2 MNIMUM   FLOWVALUES   TOBEEVALUATED  (% F                                                                                                                     di7 FlOWVALUES   TOBEEVALUATED     (%FLOW) 24 UMUUMNUYMER         OFLPISUs PERAPRU nrt"
* _
220%
TECH  SPECLIMIT  REQURED   FORCTS                               12000 22    rIANAYC  LIA0T1ECIRED   FOR ITS                               12000 I.
:ALIFRATION EFFECT  fC1                             CALBRATION   TOLERANCE
             %>CS                                                    ' RP                      %CS                               %SRP                              %CS 1 owno                                                     0.625                                                        125 20                                                                  -0621                                                        .1#2 G10 LOWtbASEOSCRAM     (39.11-0.7%)
ALRIRATDON EFFECT  (CE)                            CALIURATION  TOLERANCE                                                INGU"I
            %CS                                                      -ARP                     %CS                                %Pp                               %CS 1.00%
          .1 D0M                                                                                                                                                  .100%
41 'LOW LASEDSRAM         (11.71194%)                    [CALIBRATION ___
LOOPTESTING LUNCEI
                                                                                                                                                                   %CS 0.625                    050%                                 1.25                            100%
                                                                    .04625                                                       .125                            .1.00%                                 1.3    034G%
CALBRATION 00      WM6RTI0N  EFFEI C(E                                 TOLEFWNCE                                                    tOOPTES11INGUNCERTANTY             LOOPTESTNG  UNCE          NONTEST7NGERROR 1.DT                                                      %RP                                                         %RP                               %CS                                         %RP 0 00                                                       125                              1.O%
i te        .10000          =                                                                                                                                      -.W%
r 0-CALIBRATION 70LERANCE                                                    LOOPTESTINGUNCERTAINTY             LOOPTESTNG  UNCE
                                                                     %RP 0so                                                        125
                                                                      -050                                                       .1 25                           -1.00%                                      .30393%
93A2      EPU WJ91p LoopOpeIS Ar**I tkst4bWoib

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ALLOTHERS                        lonTeTfingError:
5                                                                                                                                                                                                                  co MmuamantAc   AtRoc          = E andon                t rRPP nroia
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12                                                                                                                                              0.000l 2                a faweem         LSp=AV- SCS1QSQRT(A35A2))_                        I n9EO liewo' 1           _1                II                                                  I                                                           SUMtN5    Ng)                                                           -I -       -        I-t51i                                                                               i                       i                          I~   ~    00001111l,1j            0O00WI? 1naftfqjeoneP              APRM&MCcrdtardo wwovrwsUmCpopljItI Ii                                                                                                                                                                     0000000if                    EOQUPUENT ALIBRATION         COFNERTEO     TO' RPANDsQJARED        E1lt2 (OIt(IWCIO)2 21 22 TotlLoopLwretrwyI ApplidNomTets"       It~r t00rr 4 3450%1 26 21                                                                                  FLOWEASSED         t&deg;t 0%)
SCRAM FIXEDSCRAMlEODXUXC)                                                   *32752%1             .3003%
SETPOENT             ALLOWABLE      Il MARGIN                  CTS. ASFOUNDTOlERAIXE (P17                                  CAJIBRATIONTOLERANCE iom25ri0 VwC                                 %RP t782%                      54e00                                              427                  4-37            lNA            43 60%                    437                               4118% -1           432              0100 03    4s
              -2470%                                                                                                                               4108%
I1 1UsIAVneSathCuwve                  3?Wd-4t DO             o 32?Wd*4t 75                                                                                                                                 2!
40                                     hilhed I A                                                                                                                                                                                           4CE
                                                                                                                                                   %CS                                                                                           %RP 43                                   -     0084                       S e50                      477                                                 4067%                                                       4&tIo%     1       4t?             0+/-22 25!53%                                                                                                                                                       460                               47.17%     I       472             5807 NCE ITS:1AV)        I        LSo                                              VALUE        FI    0m                                                                                    n 41 KCs                                                                                                                             %RP      _      %CS             I        VDC                    RP                                         . ARP adIVier SETPOINT         I ALLOWABLE           UARGI0                   CT& At FOtNDIOLERANCE IT                                 - CALRATION    TOLERANCE 04                              l_      SthodIAV   ILOIMIIF l          SETPONT                              _
(MU)
                                                                                                                                   %RP             %CS                      VCC_         l     %RP 11026 t 775%                                              111.71                     820                  936             WA              3057%                                                l     0207%     I II$"                                                                                                                              *I$
9f                 11e40 9157%                                                                                         1152t MethodI AV                                           SETPOIN CTS AS FOUUDTOLERANCEIFT                                                                                                                    ..,i ITt- AVI                                                                  VALUE             P) 2) 97                                       % YRP                                                Vck                  Vdt            %RP      I       %CS                    l VDC       I       %RP             %0CS        l     VDC             %RP I$
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Attachment 7.3 VYC-0693A Rev. 2 Yankee Nuclear Senrces                                                                Page 1 of 2 UEllERA L Q      ELECTRIC ATmIC Powra EQUIPMENT OEPARUE~NT s.cc.ac. 22AI366         "&.. -
DESIGN SPECIFICATIOR                                                     S. MCI 12           CO.r a-1.1.CCV13 I
4.4.2.1. The detector sensitivity shall be such that the output of the signal eonditfoner corresponds to the required percent pover reading associated with the neutron flux Levcl In the viecinity of the detector.
4.4.2.2. The rangp of neutron flux (operatig) shall be as specSfied on the data dect.s.
iC,4.2.3. The rage of neutron flux at 100 percent reactor power              halL bc as specified on the data sheets.
4.4.2.4. The range of gamma dose rate at 100 percent reactor pover shall be as specified oo the date sheets.
4.4.2.S. She detector shall be designed such-that the saturation character-Istics of the detector do not caSc an error In the signal due to power supply variztion* of greater than +1 percent or the 16b percent reactor pouer value over the operating nectron flux range specified :inthe data sheets.
4.4.2.6. Ihe detector shall be so designed that the true output chall not deviate fron the Ideal output by wore than +1 percenc of the 100 percent reactor power value over the top decade of the cpexatfrg fluK range specified in the data sheets.
4.4.2.7.      ~t~e detector shall have aulminun lifetine of 2.0 years in the lifetime neutron flux specified In the date sheets. End-of-life is defined as having occurred %&eathe ratio of the output uignal resulting from nentron*. -ta the output signal retulting from gas s5 tesches 5 to 1.
4.4.2.6. The detectortcable leahage eurreat shall not exceed 41.6 percent ef the full scale output during the 1iff of the detector. Leakage current is de-fined as that currant presented to the             inafl conditioning equipment     bhen the detector is at operating conditions but with no neutron or samma flux present.
4.4.2.9. The detector and detector aseaubly            nvironmnent shall he as follows:
: a. Neutron and Cmna, Tlux at Detector as specified on the date sheets.
IL  In---   IDs...   ..       etr         wrzneo Ca=&l'%,            2.4 R/hr Ieutr:Ir:           10 ren/hr
: c. ZRactor Pressure:
Operation:                    1025 pals at 546F Design,                       1250 pcug at 600'P Maximum Emergency         fressure:   1375 paig at 383'F
                                                                                          .dI, ..-
I   FEE       9 PIZ       I

Attachment 7.3 VYC-0693A Rev. 2 Yankee Nudear Services                                                            Page 2 of 2 GENERALCo ElECTRIC AtC~fC POcVE    EQUIP90Nt OPARTMt)T D)ESIGN SPECIAT                                                           c  o. 22M1366    --   .o 3 4.4.52. The true output of the aignaL conditioning equipnent shall w t deviate from the ideal output by aore than 40.8 percent of full icale at coatrol room desizn center environmental coadttioea over the range of flux (operating) specified In the date sheets.
4.4.5.3. At the control roow design center environmental conditions specified Itnthe data sheets, the equipment shall not hava a long terf drift (700 hours) gtestAr than 4(.8 percent of ful scale.
4.4.5.4. The signal conditioning equipment shall be deaSined cc thitc the gain can be set at a dasired value within 40.1 percent of the full scale value over Urc range of adjustment. The gain shall be adjustable in three steps and each step shall be continuously adjustable by at least a factor of 5.
4.4.5.5. Ihe signal condirioninz equip itt*Wall provide a 0 to 160 wtVfor xero to full scale output for the coaputer.                                                       .
4.4.S.6. The signal conditioning equipment shall provide a C to L0 volt A gual' to the Average Pever Range Monitoring Wystem. Assignment o: the various signal conditioning outputs to the APIR'a is wade on the 2nctrumenc Engineering Diagram (LED) licted 'in Paragraph 2 of the data sheets.          The signal conditioner shall be designed such that two AiRHes may be driven from each LPRH signal conditioner output.
4.4.S.7. The signal conditioning equipment shall provide a 0 to 10 volt signal to the Rod Zlock M)outor (RIM) System specifted to Paragrarp 4.6.8. The required "A core level eand C' core level couditioned detector'signale 4haIl Ub eonnected through a avItebing matrix to the RlK associated with seactor ?rotectkon Systea Trip System A. The required '" core level and ID" core level conditioned detector signals shall be coanceted through theCwitching matrix to the RUK associated %dtb Reactor Protection hysteu trip System Z. The appropriate Inpute shall be automaticelly switched upon celection of a rod. Selection details are found on the Instrument Engincering Diagtara (IED) listed in Paragraph 2 of tbt data sheets.
4.4.5.8. Signal Output to LPRN Meter Croup Display - The equipment shell be designed such that a gtoup of conditLoned outputs are provided to the IPRK Group Diapley upon selection ofa control rod. Particular selection and routing details are as specified on the Instrument Untineerlng Diagram (lED) listed in Paragraph 2 of the data sheets, 4.4.6. Trip end Alarm Fuetciat.           The folloving trip and alarns e   required::
: a. Upscale Level Alarm
: t. Devgeale Level Alarm Rp Z'1  9  f        *t,
 .        ...            . __   r........ ....>.~'

Attachment 7.4 YC-0693A      Rev'. 2 Yankee Nudlear Services                                                                          Page 1 of I GENERAL4DEETI AMC. -PCVwt    tOMPRETtOPRS4 EL~~~CrRIC               -CC      221I6A These SOMttts ate plated MXAiUsY IU the Core AS Ahovu au T1VWC !,
and w*AJLaly ts *bAxm on the Ins tusent, anglaeerizZ digram listed Lu Paraxrah 2 of theme date sheets. T. sources; sAml be Irradiated in a swten&. desccihed an the Lrradasticn specificato Ua ced on the ikutroa Sour"e DwdngLU lstod In TaWstagkph 2 of these data s!hect.
               -.       b~t. peuatrstiflaf shal be desitned and Installed esich that special conrdIa cables can be used for connection of detectors to signal conditioaing *quipimcat.
4.4.2t. Intermediate R-ange         bonitcorinit System. penetrations   -sam     as r~arar-
* 4.4.3.. rover 2Ante          )4oaitoriux Syses A. Detector sod Detector Assembly eawl be VIlaced within the core iu the wmeer shav*7La FIngure 2 of these data mlieetx.
: b. Rsapg of Operating NCeutrom Flux             hAlIT be from 1.2 x IO     nvUto 2.81 x 1014 CT.
: c. lbs !kutroa Flux at !00 percent Reascci towesr La dih yicinty of the L~ctorr shall bwe aildtn the r=uFe of 9.4 x lDnUr                  to Z.t  x  :Iuv.        The peak neutron flux at 120 percent of rated power wll be 3.4 I 10O'4at. Mme detecror signal resulting froo this fins *Isi Dot detiate from the 14*al output bj date than Claterc) percent of the 100 percant rated pwer vvlue.
: d. The cam riti at too rerceat v~aco                     roe Late                ofi.
t.ba 4etevtor shal be within the range of 4.2 X 10 Xkhr to 1.2 z la Kxar.
: v. Detector JLifetian Uuitron Flux shall be X.8L vlai)Uav -ftexvf at the asaxtum gam, flux apectIL&Cd
                              ~tz ?o~r ant Ptoitorln. 1hea the teactor paver is derbcdvt 4.44.
e% octant e7        try. Che .qvivealtt poetlteaf sW1l be as shownu Lu Ta~le L'of these data osheet.
4.4.5. Lmtace rwaer Passe oneitordnt. Use a of LWrit outpuzts eeted as L~mpc to ea AMI that vu7t bebpaff0* at a co* t~ime sball &oc excee o= four AMVi that have ten LWC Inputs (smm coatift L1Vk power" trow aoothar Weis) and' eev for K AMV thart UaS tveuty MMihaftd 1A.K13Laet.
tiodir coed Catss wlwre all L1IM afgale firon
*
* 0   ~~~~it Z         COP40               "v   sleasiag.
i4wbAasociat*A AflDIhaIontA md...e~-      a:s_..        e.
i

                                                                                           *.* '        - * *v *. *            .*.
Attachment 7.5 VYC-0693A Rev. 2 Page 1 of 3 Yankee Nuclear Services GENERALE~ EUtCTRIC
                                                     'MLE  IG       PERFORMANCE SpaC.
4   175A12S9 l., 04-0       2 emw 175A12sg                     AIX APR canu a~to -2                  Pa    I       nn~wsrmsV  voz 1t:$         a   G'IAJ3 1.0     TEMPERAIMR           AXD RflQDITY 17SA9680 parr. 1.1 1.2     1'oll                                                        175A9680 pars. 1.2 2.0     POW1ER 2.1 4-5 volts DC                                                     175A9683
               .2.2 tJ5 volt. DC                                                    17SA9698 3.0      IMMUS 3.1     LPPX 3.1.1 Polarity and Range                                     o to +10 volts DC 3.1.1 Maxdm g1!obr -to operate                               24 3.1.3 )Uinl1 %%=ber to operate in apl-c.                     10 3.1.4 Hinimaw 'numcbtt to opexat.e                           6 3.2 LI'RH Sypase                                                     1 for each LP2H 3.3 LPRH Coutm 3.3.1        lliaber                                         I                                       I 3.3.2         ftlxrity and Range                             -0.5 ma per LPRM 3.4     Calibrator rover 3.4.1        lklwmbr                                         1 for each 1X 3.4.2        Value                                           -14 volts DC nomiusl 2 to 10 vults DC nomnaL 4.0 OUTPUTS 4.1     Recorder~                                                    0 to -1 volt Output IUpqda~ce                                             1.2 ohms 4.2     Coup-car                                                     0 to -160 WV Output 7mpedance                                             215 ohm 4.3     Ketor                                                        0 to -10 volta DC 4.4 RM( Rteoroue Sigual (Isoalted)                                   o to -10 volts DC 5.0 cOMOT~LS MOD INOICAMRS~
5.1     mlode switch
                            'to.r1.
I 5.1.2 Standby. Same SW 5.1.1 except looper~attv~e krip is tripped.
5.1.3 Zero. LPR)~'t Aixgone.ctoa. DC anp can be adjustad to sey 5.1.4 Paver Tact. .Operator w7~ apply &od adjustcable ximulatod rov~er aigual uhlle stiEll co~kected to the actuzal flow sigunal.
5.1.5 Po-er and Flow Teat. Operator say apply Adjtstable A-IMulated aignolff Ffr- tbh   'Pvoo,- .. A V1 .vi P2Af~..
3 lc   .       --
         ---- , 1F
                . _   Pe ji                                                ALLrP                           175A! 259 t2A7--- Iio/,t47L               KI,    A MMMA llLX0.4 cwo-       00 a.. I
                     .~~~". , ....

Attachment 7.5 VYC-0693A Rcv. 2 Page 2 of 3 Yankee Nudear Services FEtERAL           ELECTbtI             lC        pMAsc nt .Ei-l                              ~~~TrE DEI6N b PERFORKVCE :SPEC.                    e   e    3    _a2 175A1 Z59                           A P RMt oft *o              ..
3             -WN&      0     utsW nor           ESv Co     c 51,S                   ZEl   73i_
5.2.Hater F4al-ti Swit        -         -c           .
572.1              gea   .        Ae aeac   oaput of     of SLeRHs Dty  sueaed.                                                                         jtu S.2.2 rcw. Output                     fromFoberverr          fnic.n
                           . .2.3            countt    terRbe of  S             bc ng Averaged._
Kleter mding ic S tiec the oer. r.                                                .
5.2.4 A1 A6, IBl-BA6, C1-06, DI-D6. Meter                                                                _
rea    output of each I.MK. Select$5 calibrator power from observed L1RK.                                             5~
5.3         Merxr Revrse. Expand Switch                                                                          ,
5.3.1             Reverse                                            1 volt f.s.                         CY 5.3.2 lb                                                    .       10 VoLtC f.c.
5.3.3 X10 '2W                                    '                  1 volt f.s.
5.4         ?ower Test Potentiometer. Adjustable miulated Power Signal; Range-zero to greater than fall actle.
5.5          Flow Test Potentiometer. Adjusteble aimuLated XE3ow signal; Ren.-lesa than ceto to greater than 1001 rov.
5.6          Calibrtian Ajust Potentiometer. Controls voltage to precision resisters of CaLibrator Range-0 to greater than -10 volta DC.
5.7         Calibration Monltor Switeh. Alovs Calibrator voltate to be viewed ac eer.
5.8           PRX 3bypucd Light. Indieates vben LM beng Msitored is in the .Calibrate or Bypasted condition.
5.9          Keter kpaa6 Light. Indcates when the meter J                     lReverse. XPal Switch is is a position otbeT than XCIVIA.
S.10              rip temet Switch.                 Resets a1l     latching trip:s In the Aram and Associated UIm's.
6.0      PERFORHAKCE 6.1 Averaging Circitry 6.1.1 Accuracy (inciudes Lizearity and Stability)                                                                        A7 Xstrictod Condltlo                                '0.e2 mUll CondItions                                   '2.42 6.1.2 Drift                                                          00.5X/2 ueeks 6.1.3 Respaose Time                                                    5s                            .M 6.1.4 Cain                                                           2.5'640%
6.2 Trip Circuits (Mo-Tloov iisaed)
Spees. apply when using Quad Trip Unit 13611322 a3d Irip Reference Unit 136R1321.
    ._F I.
                  ~
d_.
                   ,.a,
                        .tA~e~i  ,.. I7 I ,   ,  s  .   .
SA .QSE      CAL1FORMA K:     O l

                                                                                                     .~~~~~~~~~~~~~~~~~~~*.
Attachment 7.5 TYC-0693A Red'. 2 Yankee Nuclelear Services                                                                        Page 3 of 3 Yankee Nuclear Servrces CEI4ENAL~RECTA ICt w
175A1259 IF             .3 V'    -.A                             T'           DESIGN I PERFUO14ACE SPEC.
17SA1252.                lAP R K
        ~    M*.~         F Am* 3           InASTWO4AE~et                           STA STAKM~3     S~ Pat.7..3 W.=O*a 6.2.1 AccUrRC7                                                                                            PA Restricted Conditions                             *j2f.
t2X f.is k
Tdl Cou4LtLons                                                                                   to 6.2.2 MMif                                                  'O.5112 getks                           410 02 I :j     1 6.3. Trip Circultrs (Fiw Biased) spe~ca.                                                                    P.
                         *pply wiben using Quad Trip Unit L36EL322.
Trip Rerereate. Unt LL36R1321, and Trip                                                                   It-I Dia" Unit 2L6X541.                                                                                         F". 1 6.3.1 Accuracy                                                                                            0 41 6.3.1.1 Ret'ticted Canditionc 50 to 1oot flou 0 to 501 floe X21 92Z
:51 W
6.3.1.2 Full Conditions SO to 100% flowe O to 50% flou 6.4     Count trip Reierence,                                       '11 6.4.1 LUee~rity lestrrcted Conditions Full Couditions lestricted CoodItions                             *'12 Taul Canditionx                                                                                        .4 6.4.3 Drift                                                 '0.522 w.eeks 7.0 CSTRUMctOf 7.1      c*rds 7.2     )'adulas 7.3     MAched-4-l Xig A.0. TEST REDUIROD1{T                                                           17SA1299 A7 I.
     .pzV.-q-fi                '.f.7                41'/b        ISAIN JOSE. CALIFORNI       "1        17F541259
          -    -     A-                                                L         t.                        ,-   .           C4"     .   -
ADV)~A     IfP Nfi                               .-
yr-.t'- ~ I  ..-..

Attachment 7.6 0                           Co E Nlu clear Energy                       VYC-0693A Rev. 2 REVISION STATUS S1{FZT            Page 1 of 23 DDC TITI.E       VIAOlV CONTROL TRIP RFFERENCE CARI1                             . ...      _ .     .. _
LEGEND ORPFSQR1TON OF GROUIPS                                    TyPJ+      DS( 3N SPEC.
I - DENOTES CHANGE FdF.      OF) HON [A MPL ITEM.:       NA                            -
JEEP CLASS )E.
'11h1S ITM IS OR CONTAINS A SATTETY RELATID ITEM         Yns I75-1Non              EQUIP CIASS CODE     A REVISION                                              C 0     RM.01079                 JUN20. 1994 I    R.A. SEARLES            FEB OR. I99       RJA CN02 137 CII K BY: R.A. SEARLES ENGR:     C.J. M1IXI.ER 2     R.A. SEAR          09                   i CKN084         -
CHYK BY: R.A. SEAtLES ENGR:     SI). SAWYER PRINTS TO MADE BY                               APPROVALS                       GENERAL El.FXrC COMPANY 175 CURTNkR AVENUE C.J. MII1.F.R     FEIv 09. 1994      P.J. KINDER     JUN 10, 1991    SANJOSE CALIFORNIA 95125 CIKED 1W               .             ISSUED 24A5215 R.A. SEARI.FS      JUN09. 1994        R.J.AHMkANN     JUN20. 1994     CONTONSIIEET 2 L6-XS

                                                                                            . ..   .    .    . Z. . -
0                                                       24A5215           Si NO. 2 GE Nuclear Energy             Rev 2                OF 19
                       ..         ~~.
                                    ......                    I Flow Contirol Trip Rcference (F7CTR) Card               DESIGN SPECIFICATION TABlE OF CON TFrTS L         DOCUNFNIT L)ESCRIPTIO-                                                4 1.1       DOCUMENT PURPOSE AND USE                                             4 1.2       DOCUMENT SCOPE                                                       4
: 2.         RELATE[P DOCUMENn                                                    A 2.1       REQUIREMENTS                                                         5 2.2       AiPLICAULE STANDARDS                                                 5 DrESCRIPI IN 3.1       GENERAL.                                                             6 3.2       PH JYSICAL.                                                          7 3.3       FIRMWARE                                                             7 4-        QUIRATIONAI, PERFORMANCE                                             7 4.1       ACCURACY                                                             7 4.2       StRVJCE LIII-I                                                       7 4.3       I'OWER REQUIREMENTS                                                  7 4.3.1     POSITIVE LOGIC CIRCUIT SUPPLY VOLTAGE                                8 4.3.2     POSITIVE ANALOG CIRCUIT StJPPI.Y VOLTAGE                             8 4.3.3     NEGATIVE ANALOG CIRCUIT SUPPLY VOLTAGE                 ,
4.4       SAMIPIUTIME                                                          8 4.5       ANTI-ALIASING FllTFR                                                 8 4.6       RER'S9'ONSE TIME                                                     9 4.7       AUT1OMATIC TRIP REFERENCE SELECTION .                                9 4.8       RF.CIRCULATION DRIVE CORE FLOW TRANSFER FUNCTION                     9 4.9       POWER BzASED ADJUSTMENT ADDER                                        9 4.10      Al,lTl.RNATF. TRIP REFERENCE SELECTION                               9 PROCIRAMML                 OAT] N                             -O S.l 5.1       TRIP REFERENCE ARRAYS                                             . 10 5.2       TRIP REFERENCE FUNCTION SPECIFICATIONS                                10 5.3       SIGNAL VALIDATION                                                     10 5.4       AUTOMATIC SETI)OWN SETP'OINT                                          10 Attachment 7.6 VYC-0693A Rev. 2 Page 2 of 23

                                . .. .. . " " - .. . .. .. . . .   .7 1-    .... .            . .:.1.
24A.5215        SH NO. 3 a                   GE Nuclear Energyr TAIIIQE QF CONTENTS 6&      SPECIFIED 1/O CHARACTERISTICS                                                    I 6.1     INPUTS                                                                            It 6.1.1   ELECTRICALINPUTS                                                                  11 6.1.2   LOCAL OPERATOR'S INPUTS                                                           1l 6.2     OUTPUTS                                                                           12 6.2.1   ELECTRICAL OUTPUTS                                                                12 6.2.1.1 FACTORY TEST OUTPUT                                                               12 6.2.2   LOCAL. OPERATOR'S INI)CATION                                                      12 I.            IFIED MECJHANICAL CHARACTERISTIC                                           1 7.1     METAL CASE: (RW' 3 - early BWR 4)                                                 13 7.2     SMAL.LI- 44P N: (latc BWR 4 - BWR 6)                                           . 14 L       I3LOCK DIAGRAM                                                                    I5
   . SP'EC'IF F.D OPERATING ENVIRONMENT                                                16 9.1     TlMPFRATURE AND HUMIDITY LIMITATIONS                                              16 9.2     ELECTROMAGNETIC INTERFERENCE                                                      17 9.2.1    SUSCEPTIIRILITY       .                                             -            17 9.2.2    EMISSIONS                                                                         17 9.3      AMBIENT PRESSURE LIMITATIONS                                                     17 9.4      RADIATION EXPOSURE lIMITATIONS                                                   is 9.4.1    DOSERATlE                                                                        18 9.4.2   TOTAL DOSE                                                                        18 9.5     SEISMIC DISTURBANCE LIMITATIONS                                                  iS I (L    SAELTY PRF.CAUTIONS                                                              p; 10.1    PERSONNEL SAFEITY                                                                 19 I +/-      TEST 8E:QV!RF,9EMlN                                                              12 11.1    AUTOMATIC SEIF-TEST.                                                              19 11.2    MANUAL SURV'EIl.LANC'rE/CALIBRATION                     .                         19 Attachment 7.6 VYC-0693A Rev. 2 Page 3 of 23

GE Nuclear Energ' I24A25159 Rev 2 SH NO. 4 OF I 9
: 1.       DOCMtENIF        D.SCRTf'ION aT 1.1      DOCIIJIMENT PIRPOSE AND USE This Design Specification describes in quantitativc terms the characteristics of the FLOW CONTROL TRW RFEERENCE CARL).
Thcsc characteristics are grouped as follows:
* Inptits to the card - their information content and clectrical characteristics
* Outpuls from tli card - their inrormation content and electrical characteristics
* The functions of the card - its information processing, transfer functions, and the intcrrelationships between thc inputs and the outputs
* The physical env'ironment under which the card will function properly
* The card's physical parameters - size, shape, type and placement of connectors
* Application information - potential safety hazards 1.2      D)OCUIMENT SCOPE This document describes the performance or the FLow CONTROL TRIP RIFF.KRENCfl CARD with respect to its use as a component part.
Attachment 7.6 VYC-0693A Rev. 2 Page 4 of 23

2 24AS21;       Sli NO. S GE Nuclear Energy                      Rcv2              OF '9
: 2. RFtElATFI) IOCUME1FNTh 2.1  REQUIREMENTS a)   RWROG Hardware-Related Task Authorization for Stability LTS Enhanced Option 1A: 94.159.0, .S, 95.159.0. .5. .7. 96.159.0 b)   NUMAC Requirements Specification: 23A5082 c)   NULMAC Soflware Configuration Management PHan 23AS 161 (meets requirements of ANSIIIER 7-4.3.2-1982) d)   NEDO-32339-A Class 1. December 1996 - Licensing Topical Report, Reactor Stability Long-Ternm Solution Enhanced Option 1-A e)   )rNEDO-32339-P Supplement 2, Enhanced Option 1-A Solution Design, April 1995,
        . vith errata 91I/95, 9115J95, 1/31196, 3/27/96, and 11/27/96 I)  NEDO-32339 Supplement S. Enhanced Option l-A Solution Ciosure, September 1996 2.2 APPLICADIU&        STANDARDS
: a. MIL HlMIK-21717 Reliability Prediction of Electronic Equipmcnt
: b. COl 265A1 14R Specification for Printed Circuit Boards C. IEE-1P.323-1974 QualifyingClass lF Rquipment for Nuclear Power
: d. IE-FF' 344-1975 Seismic Qualification of Class lEEquipment for Nuclear Power
: e. GE I100 Series Electroniagnctic, Irterfercnce and Susceptibility Attachment 7.6 VYC-0693A Rev. 2 Page 5 of 23 II

*1 j14AS215            St[ NO. 6 0                        GE Nuclear Encrgt,
: 3.       y)1SCRIPTION 3.1      GFNERAI, The FLOW CONTROL TRIP REFERENCE CARD is a Class IE component. This card provides all of the functions required by the original equipment and secrion 2.2 and uill not deter from the current mechanical parameters or electrical connections in order to implement new features, unless otherwise requested. Logic common, if not present at the connector, will be connected to present unused pins. In addition, this card provides input flow signal 'validation to ensure fail safe operation. This card may be inserted and removed under power without danger and will automatically reinitiate after competion of an internal self-test (approx. 5 sec.). This card provides for the following interface between the input flow and the output references:
* Provides flow signal output following noise & EMI filtering.
* Provides a Scram Trip Reference based on a derived core flow function residing in memory for the recirculation Two Loop Operation. Two Loop Setup Operation.
Singie Loop Operation and Single Loop Setup Operation settings.
* Provides A control rod block Trip Reference based on a derived core flow function residing in memory for the recirculation Two Loop Operation (TLO), TLO Setup.
Single Loop Operation (SLO), and SLO Setup settings with slope and offset
         .adjustmeont.
      . DIP switches provide selection of alignment constants for the Recirculation Drivc/Core lFlow transfer function.
DIll switches provide selection of an alternate set of trip reference function tables.
* DIP switches provide constants for the Power Based Adjustment transfer function.
* Provides a recorder output of the control rod block Trip Reference with offset adjustnent.
I  . Provides validation of incoming flow signal (out-of-range high or low).
* Provides an INOP output contact that is actuated if the card is not operable or fails self test.
* Status IXE:1) provides visual latchcel confirmation of status (INOP).
* Status pushbutton provides reset of status (INOP).
* Setup LED provides visual Iatched confirmation of setpoint Setup condition.
l      Setup pushbutton alternately changes between SET UP and NORMAL setpoint arrays.
* Provides for autnmatic reset of trip reference setpoints to normal based on a preset control rod bloclz trip reference value.
Provides a factory test output.
Attachment 7.6 VYC-0693A Rev. 2 Page 6 of 23 i

                                                      . .-1 ...... ...: -, ': ::    ,     .:.. ',. -'.
                                                              'I24A5215          SH NO. 7 0                         ;GE NudclearEnergi'                    Rev 2              OF 19 3.2       PYSICAl, The FLOW,     CONTROL TRIP REFERENCE CARD is designed in two different size configurations. The FLOW CONTROL TRIP REFERENCE CARD is designed as a pin-compatible replacement for the existing PCTR Card in the APRM page. See Secton 7, Specified Mechanical Characteristics, for details.
3.3       FIRMINVARE This card contains firnnware for providing recirculation drive flow based selpoints associated with tile input-output interface.
: 4.        01FRATIONAl, PERFORMk1AN(CE 4,1      ACCURACY The r4LoW C(ONTROL TRIP REFERENCE CAR) will be designed to operate with an accracy of il .0 % over 36 months due to environmental, initial calibration and accuracy drift; 4.2      SERVICE LlFE The target service life for the FLOW CONTROL TRIP REFERENCE CARD is to operate continuously (within the specificd environmental limits, and allowing for rcplacernent of failcd components) for at least 40 years.
4.3      P'OWER IIFQIJIREMENTS This card will require I 15 VDC. -15 VDC. Analog Common & Digital Common for nornal operation. Digital Common will bc-required for EMI grounding purposes even though +5 VDl is not being used. The +5 VI)C will be generated on board from the +1 5 VDC. The card connections will be compatible with the present pin-out configuration in thle APRM page connectur with the D)igital Common it connected. taken from the present logic common pin-out. If not conneced. then the logic common will be connected to present unused pins. The power requirements of this card will not adversely affect the APRM pwages power supply capability. Application and tolerances arc listed below.
Attachment 7.6 VYC-0693A Rev. 2 Page 7 of 23

Ri                                                 7~~~~~~~~~~~~~~~24A5215 S1 NC). B GEENucearEnjergy                           Rev 2                  OF 19 4.3.1     POSITIYV LFOI  , iC CIRCUIT SUPPLV VOLTAGE (Generated on board from the -ItI5 VDC & Analog Common)
Application:       +5Volt DC power used for internal lokc.
PARAME1ER           SYMBOL        MIN,      OPERATING          OPERATING           MAX      UNITS
_______    LIMIT         MAX                 _AX M               LIMIT      _
Logic Supply         Voc          0            4.5                 55               5.5     VDC vollagc                              I_ ________
Logic Supply         Voer         0     l     0.00                 0.05            0.10    VRMS Ripple Voltlgc I____                     II                                   _  II_
4.3.2 POSITI!F, ANAIO('V CIRClJT St)PPIV VOLTAGF, Application +15 Volt DC power used for intcrnal ADCs, DAC's, amplifiers, etc.
PARAMETER           SYM11L        MIN       OPERATING( OPERATING                    MAX     UNITS LIMIT         MAX           -      MAX            LIMIT Positivc Analog        Vdd          0             14                  16              16     VDC Supplv'oitagc Analog Supply        Vddr          0           0.0o                0.01         j    .10   VMIS Ripple V'oltagc a                     -
4.3.3 NEGATIVE ANALOG CIRCUIT SUPPL11'VOLTAGE Application:      -I1 Volt DC power uscd for internal ADC's, DAC's, amplifiers. etc.,
PARAMIrI'l;R        SYMBOL        MIN       OPERATING          OPERATING           MAX     UNIT7S
_LIMl1        MAX                 MAX             LIMIT Negalive Analog          Vss         0            -14                 -16            -16     VDC S~upply Voltag e    ._ _  __ _       _  .__     _ .__
Analog Supply          Vssr         0           0.00                 0.01           0.10   VRMIS Ripplce Voltagc                            _
4.4       SAMiPLE TIME The minimnuni time for sampling the flow input is 4 msec. The interval for updating the trip references is 28 nisec.
4.5       ANTI-ALIASING FII.T'ER The flow input anli-aliasing filler is scl at <201 Iz.
Attachment 7.6 VYC-0693A Rev. 2 Page 8 of 23

24AS15              SH NO. 9 0                        GE NruclearEnergy                    Rev 2                  OF 19 4.6     RESIiONSEOT1NiF.
The maximum response time from input to output is 250 msec, 4.7     AUTOMATIC TRIP RFEURENCE SELECTION Trip reference functions are identified as setup and non-setup. Whcn the control rod block selpoint exceeds a specified Automatic Scidown Setpoint, the trip reference functions are laken fron the non-setup tables, even if the setup selection has been made with the pushbutton sciector switch provided.
4.8     RFCrlRCULATION DRIVF. CORU FLOW TRANSFER FUNCTION Thc Recirculation l)rive/Core Flow transfer function wilt be adjustable to accommodate variations in this relationship. Two four-position DIP switches. operating in binary, arc used to select the appropriate alignment constants used in the transfer fanction. There will be a maximum of sixcecn chniccs for each of two alignment constants.
4.9     POWER4 BIASED AI)Jl1ST IENT AIMER The Power Based Adjustmcnt Adder provides an adjustment to thc output trip referencc scipoints. Thc samc adjustment adder is applied to both output trip references. Three of four switches arc used to provide eight choices for the adjustmcnt adder. Selcction of an adjustment adder ol zero results in no adjustment to the output trip references.
4.10   AL F:RNA'F T)l' REFI RENCE SELECTION Two conmplete scts of trip reference arrays are stored in memory. One switch of a four I1)V switch is used to select betwcen SETI (primary) and SET2 (altcrnatc).
Attachment 7.6 VYC-0693A Rev. 2 Page 9 of 23

: :   '.. k.,:. , %,
GR2NAclear Energr I24AS21S Rev 2 SHiNO.IO0 OF 19 S.           PS'IOGRA j 11NG INFOR(IATION s-1          1TIP REFERENCE ARRAYS At least 512 points (9-bit resolution) composing an array of each specified function (plant specific) uill be held in meniory. There will be up to a maximum of two sets, each consisting of eight (8) transfer functions. Thesw functions are programmed into the memory component (inslalled on a EPROM) and can only be changed by component replacement .
5.2         TRIP REFERENCE FLINU'Y]ON SPECIFICATIONS The 512 point, (9-bit resolution) tables for each plant-specific trir reference function are specifies as:
: 1.         Single Loop Operation (SIO) NORMAL
: a. Sciamt
: b. Control rod block
: 2.          Two Loop Operation (TLO) NORMAL
: a. Scram
: b. Control rod block
: 3.          SLO Setup
: a. Sclam l               .tControl rod block
: 4.          TLO Setup
: a. Scram l             h. Control rod block-These functions are progranimcd into the memory component (installed on a socket) and can only be changed by component replacement.
5.3        SIGNAL V'ALIA)ATJ0N The input recirculation drive flow will be vaidated to confirm that it is not out-of-range N(high >130 or low < -1S%).
IS5.4      AUTOMATIC SUTIJOWN SETPO1NT The Automatic Setdown Sctpoint is provided fir each pair of TLO (NORMAlJSETUP) and SLO (NORMA14SE:TUI') trip references. Tblic setpoint is programmed into EPROM.
Attachment 7.6 VYC-0693A Rev. 2 Page 10 of 23

                                                          . I I    - .. - ..  . .:,. - .I :,.. I . , .. .. .. . . .. .. ..
                       . . . . . . . .       .. .1 I . ..
.1 a                         GE Nuclear Energr I24A.5215 Rev 2 S11 NO. II OF 19
: 6. _SPCIJ'ED 110/ CIARACTrFERISTIcS 6.1     INKITS 6.1.1      LFla.('5ICAL INPFlTS
: 1.      Input Flow: 0 to l0 volts DC (relates to 0 to 125 % Dow)
Input impedance, Z., is 1001C.
6.1.2   ILOCAl. OPERATOR'S INPUTS I 1. Recirc TJ.OISLO (switch allows choice)
: 2.        'INOP Reset (pushbutton)
: 3. Recorder offset adjustment
: 4.      SETUP (pushbutton - altcrnate action)
: 5.      DlIP switches for drive flow aligrnment constants, power-based adjustment' constant, and Alternate trip reference selection a)      Manual Reset:
: 1. Pushbutton
: 2. Change in switch status (TLO/SLO) b)      Automatic Reset:
1 I From SETUP to NORMAL of a specified rod block setpoint corresponding to 5m/. recirculation drive flow above A'not      o
: 2. flower failure
: 3. E1xiting INOP IUpon reset of SETUP, current recirculation TLO/SLO switch setting will determine the applicable arrays applied Attachment 7.6 VYC-0693A Rev. 2 Page 11 of 23 j;.

l4AS2l5 Rev2 SH NO. 12 0F 19 a                        GE Nuclear Enervg 6.2      OulTPuiTS; 6.2.1    EIVC'l'RI CAI, OUTPUTIS
: 1. Output Recire Drive Flow: 0 to 4 10 volts DC
: 2.      Scram Trip Rererence: 0 to -IO volts DC
: 3.      Control rod block Trip 

==Reference:==
0 0o-10 volts DC I          4.
5.
Control rod block Recorder, 0 to I volt lC with an offset of* 100 mV INOP: normally open (N.O.) contact, non-latched. Open, non-energUize, on INOP.
A'nom - the highest flow in operating domain associated with Restricted Region of recirculation drive flow transfer function (plant specific),
A critical ScIf-test fault 2erocs the Scram and Rod Block trip references (forces APRM1 scram and rod block) 6.2.1.1 FACTO0R' TESt1' OITPllT Single digital fiber-optic communication output, transmitter only, at a data rate of 19.2 ki Iz. IlewIctI-Paackard I IFBR-1414T fiber-oplic. transmitter.
6.2.2     1..OCAI. OPERATOR'S INDI)CATION I. A non-latched two color LF.D)to indicate trip reference setlup condition. 1l2[) color      *.
indications arc:
* GREEN:                         Normal boundaries
* Y Lt.WOW:                      Setup boundaries
* YEULOW (slow blink):           Flow validation inhibit (normal boundaries)
* YELLOW (doublc blink):         Flow validation inhibit (setup boundaries)
: 2. A latched two color L.ED)to indicate card INO1P Status. LED color indications are:
* GORFN:                         Operating Normal
          . REED (steady):                 Current INOP (self-test fatllt)
* RED (slow blink):              Previous INOP, cleared, but not reset (Initial power-up or previous self-test fault) *
* RED) (fast blink):                Flow validation fault
* RE!DIGRF.'.N (fast blink): Previous Flow validation fault *
* OFF:                              No power lo card a  Previous INOP or flow validation fault is reported and reset in thc order ofoccurrenc.
2  Nonrlatcdcd Iran INOP occurs (RED) and then clears automalically, this indication will be latched RED-blinking) which indicates norinal opcration but with a past INOP. his can bo tesct by thc WInQRcset pushbutton.
Attachment 7.6 VYC-0693A Rev. 2 Page 12 of 23

24A 21F            '31 SH NO.
GE Nuclear Energy                   e             OF 19 E. ""~1W)M~AIALCI~~E1TG 7.1 MELTAL, CASE: (11WR 3 - txrly IRWR 4) 0D920 ;00 1,     -. 2D.
WIOP LEt)
INOP RESET PlISHBlrYTON NoRmAusInTr LED NORMAUSMP PUSHUUtIrON 4.250    '03                      (ALTENATES IhEarEEN NORMAL & SUIP ARRAYS)
TLO/SLO TOGGLE SyTCH (LOWCNG LVER)
RECORDSER OFMET ADJVSTNMIP EMI sill)ltn Attachment 7.6 VYC-0693A Rev. 2 Page 13 of 23 i

I.-       .
3-
:S
:@:v
:0 v :*
                                                                                   *.** 6 . .)
I S     f6GE Nuclear Fnergp 7.2 SMALL- 44 VJN: (1a(lt BWR 4 - BWR 6) 24A5215 Rev 2 SH NO. 14 OF 19 St} 06 ECTR 11N0P L.ET)
                       %. me VA           PUSHBUrlON 14ORMAUSEIIJT       IXK SE I I NORMAIJSJ3TIJ 1USHOIU1?TN (ALTI3RNAU1S DEIMWEiP NORMAL &-SETUP ARRAYS) 4.484+ &deg;&deg;
                                 -TLIO!SLI         TODGGLE SWITCH
                     ; OPMI~
(LOCKING LEVrER)
P.P~CORPEFR OWFSEr ADJUSTMENT
                       ]   '        OCARD) VECTOR Attachment 7.6 VYC-0693A Rev.2 Page 14 of 23

                                                                                                      -. . : . - : - ..-.. . .: '.".. '.- :. :.-..:. ..:.'. ..7....
J.
j24ASMt                        SliN.IS' GE Nuclear Energy A.BOKDITl~
                  -- DIOCK DIAGRAM -
Attachment 7.6 VYC-0693A Rev. 2 Page 15 of 23

i 0                            GE Nuclear Energy I24A5215 Rev 2 S1IINO. 16 OF 19 9,       NPECIFIF,) OPERATING FNVIRONMIENT The FLOW C:ONTROL TRIP REFERENCE, CARD will not adversely affect or be affected by the operation of any other components or equipment operating within the same environmenl.
9.1      TEMIPERATUIRE ANI) IfIIMIDITY LIMITATIONS Tbis card will perform all specified functions correctly when operated within the specified temperature range illustrated in Figure 9-1 and the, specified relative humidity range illustrated in Figure 9-2 (Applicable Standard 2.2 c)..
Figure 9-1, Temperature Limitations (0 C <Ta <70 -C) 4    -                                  Temperature (C)       --
                 -5        0                                                70      85
{. .    (   -    <Range of correct operation       l-       -l                  I Temperatu re                                                                        Temperature helow which                                                                          above which card may lie                                                                        c\ may be card damaged             Ranges in which card may or may not operate correctly           damaged Figure 9-2, Humidify Iimitaintns (20% < Relunmiditfy      90%)
4-                                       ReAtiV lumidity (%)
ICI      20                                                  90    95 4--*    4-   ----    Rangc of correct opcration   -*
llIumidity                                                                          Humidity below w h;ch                                                                        above which card may be                                                                          card may be damaged             Ranges in which card may or may not operate correctly            damaged Attachment 7.6 VYC-0693A Rev. 2 Page 16 of23

                                                                                           .  ,.      -, .:, .: '    .      0
: -, I ..: .
                                                                     -  .  -                 . a    :  . .-                       .. .         .
I24A5215           SH NO. 17 a                         GE Nuclear Energr                        Rev 2                   OF 19 9.2         ElElcTi'6OmA(GNETIC INTERFERENCE IThe FCTR card is qualified for electromagnetic compatibility (EMC) by type testing and analysis. The IMC testing performed eliminates the need for utilities to perforni in-plant electromagnetic environment surveys in accordancc wilh EPRI guidelines (Reference 7).
9.2.1      SUSCEPTIBLITY Thc FCTR card is mounted within the existing cabincts of the NMS and derives power from NMS power supplies. Therefore, power and signal conducted inoise immunity arc not significantly affected by the replacement or addition of these cards. The existing power.supply immunity to conducted noise and power surges remains unchanged. Thus, the only EM( susceptibility tests performed on the FCTR card are:
* Electrostatic Discharge (ESD) - 1WC-801-2
   . Simulated lightning Strike Conducted Immunity Test (using pulse measurements provided by Untergy Opcrations. Inc.)
* Radiaied Electric Field Test (demonstrate that adequatc margins exist for proper FCTR operation when installed into an existing NMS page under electromagnetic near-ficld emissions from adjacent cards) 9.2.2      EMISSIONS The radiated emissions test confirm that the FCTll card has sufficiently low near-field emissions as to not affect the existing NMS pages. Similar to 9.2.1 above, there is no accepted test level for this application. therefore, it must be established as follows:
* Radialed Tilcetric Field 1est (demonstrate that adequate margins exist for adjacent cards to operate without electromagnetic near-field interference from the FCTR card installed into an existing WMS page) 9.3       AMIBIENT I'RSSUIRE LIM       NI TATIONS This card wVill perform to specification for any absolute pressure in the range of 13 psi to 16 psi.
Attachment 7.6 VYC-0693A Rev. 2 Page 17 of 23 r

                                                     .         .       ~~~~~
                                                                                    -   .' . .  :.: . ~.:
0                         GE Nuclear E7nergy                    IRev 24A$215 2
SH NO. 18 OF 19 9.4      RiUIlATION EX'POSURE LIMITATIONS 9.4.1   DOSE RATE I The card will perform to specification over its design life in a gamma field of 3 mRlhr or less.
9.4.2   TOTAL DOSE IThis   card will perform to specification ovcr its service life for a total integrated gamma dose of ixlIO Rads.
9.5     SEISMIC D)ISTURBANCE LIMITATIONS The FCTR Card will be qualified based on applicable areas described in IEEE 344-1975 (Applicable Standard 2.2-d). The APRM page cnvironment will be established through analysis, and it will be determined that the addition of the FCTR into the APRM page will not significantly degradc cxisting system performance when subjected to seismic events.
Ioctimcntalion will show that qualified tests and levels (or analysis) cover APRM page environnmeint for this application.
: 10. SAFEWT PRECAUTIONS 10.1    PERSONNEL SArETV
* sI.P..C.TR1CIAL No voltage greater than 28 volts + tolerance (for Status INOP contact) is prcsent on this card. This card may be removed under power without danger.
* ME1CiANICAL No moving parts will cause personal danger.
* 3iPMAt, None: no high temperaturcs are present on this card.
     . R~lQI O(;lClD~
Nonc- no radioactive materials are incorporated into this card.
None - no corrosive or toxic substances are incorporated into this card, Attachment 7.6 VYC-0693A Rev. 2 Page 18 of 23 I
:.1

.4 24AS215                SH NO. 19 GE Nuclear Erergy                    Rev 2                          OF 19
: 11.      TEST REONRFEMNTS 11.1     AUTOMATIC SEILF-TEST An automatic self-test feature will be used on this card. This feature will automatically test at least once per minute. If an error or occurs an INOP will be initiated.
* A known internal reference is used, with its outputs, Scram & Control Rod Block Trip Refercnces, internally checked against the expected outputs to verily correct system operation.
* The voltages; power, logic. & reference are monitored to verify they are within tolerancc.
* The CPU monitors powcr failures to ensure fail-safe operation.
* Watch dog supervisory circuit is used to ensure correct soflware operation, cycle timing and logic, power failure.
* Voltages from the PAC are fed back through the ADC to ensure correct hardware conversion operation
* ScIf-lest diagnostic testing ensures correct DAC operation and sets its output to "O" if the signal is not updated (frozen).
11.2     IhIANIIAL SUKRVfIA.,ANCFJ(:AllBRATION Manual surveillance will be required at least every 36 months. This wilt consist of inputting an existing exictnally known simulated recirc dr;ve flow signal to verify correct system operation.
Test points are provided for measuring the power voltages (+5 VDC, +I5 V'DC & -15 VDC) and the system clock (16 h1lb?).
Attachment 7.6 VYC-0693A Rev. 2 Page 19 of 23

Sheet 20 of 22 I a              GE Nuclear Energy                                   Rev 2 PROPRJUFTARY                                     24A5215 l     9.2.2 EMISSIONS Again, there is no accepted test level for this application, therefore, it must be established. The test levels for ernissions for the APRM page will be established by the following:
* Qualifry new FCTR CARlD per emission test at derived susceptibility qualification level above
* Document how qualified tests and levels cover APRM page environment for this application 9.3 AMBIENT PRESSURE LIMITATIONS This card will perform to specification for any absolute pressure in the range of 13 psi to 16 psi.
9.4 RADIATION EXPOSURE LIMITATIONS 9.4.1 DOSE HAT1F This card will perform to spccification over its service life in a gamma field of lxIOF-5 rads Isec or less.
9.4.2 TOTA1 1)OSF.
This card will perforni to specification over its service life for a total integrated gSamnia dose of lx01E4 rads.
9.6 SEISMIC DISTURBANCE LIMITATIONS The FCTR Card will be qualified based on applicable areas described in IEEE 344-1975 (Applicable Standard 2.2 d). The APRM page environment will be established through analysis, and it will be determined that the addition of the new FCTR into the ATRM page will not significanIly degrade existing system performance when subjected to seismic events. 1)ocumentation will show that qualified tests and levels (or analysis) cover APRM page environment for this application.
Attachment 7.6 VYC-0693A Rev. 2 Page 20 of 23

Sheet 21 of 22 I at             GE Nuclear Energy                                 Rev 1 PROPRIfTAIRY                                   24A521 S
: 10. SAFETY PRECAUTIONS 10.1 PERSONNEL SAFETY
* IEhECTRICAl, No voltage greater than 28 volts + tolerance (for Status/INOP contact) is present on this card. This card may be removed under power without danger.
a   MECHANICAI, No moving parts will cause personal danger.
* Th RM AL None; no high temperatures are present on this card.
* RADIOLOGICAL None; no radioactive materials are incorporaled into this card.
* CHEM ICA]
None; no corrosive or toxic substances are incorporated into this card.
: 11. TEST REQUIREMENTS 11.1 AUTOMATIC SELF-TEST An automatic selr-test feature will be used on this card. This feature will automatically l test at lea-t once per minute. If an error occurs an INOP will be initiated.
l
* A known internal reference is used, with its outputs, Scram & Alarm Refercnocs, internally checked against the expccted outputs to verify correct system operation.
* The voltages; power, logic & rcfcrence are monitored to verify they are within tolerance.
l
* The CPU monitors power failures to ernsure fail-safe operation.
I
* Watch dog supervisory circuit is used to ensure correct software operation, cycle timing and logic power failure.
Attachment 7.6 VYC-0693A Rev. 2 Page 21 of 23 t.-I

I                                                                  Sheet 22 of 22 GE Nuclear Energy                                 Rev I 0
PROPRIETARY                                  24AS215 11.1 AUTOMATIC SELF-TEST (con't)
   '*     Voltages from the DAC are fedback through the ADC to ensure correct hardware conversion operation.
I   Seir-test diagnostic testing ensures correct DAC operation and sets its output to 'O" if the signal is not updated (frozen).
11.2 MANUAL SURVEILLANCE I CALIBRATION Manual surveillance will be required at least every 36 months. This will consist of inputting an existing externally known simulated recirc drive flow signal to verify correct system operation.
Test points are provided for measuring the power voltages (+5 VDC, +15 VDC &
I -15       C)and the system clock (16 FMz).
S Attachment 7.6 VYC-0693A Rev. 2 Page 22 of 23

Attachment 7.6 VYC-0693A Re,. 2 Page 23 of 23 FCTR Accuracy & Drift The 14BC6411 Digital FCTR card (schematic 105E1374) has an analog front-end consisting of an analog mux (233A3701 based on the ADG516A), quad op amp (233A3709 based on the AD713),
and 10-bit AID (2-bit precision within the 233A3692P001 microcontroller based on the 80C517A).
The major contributor to accuracy over the calibrated range of Drive Flow (0 to I OV) is the resolution of the microcontroller's AID. This provides 844 counts or +/- 0.47% resolution with the 2-bit precision. The analog mux, input op amps, and precision feedback resistors provide +/- 0.12%
accuracy. This yields (SRSS) an accuracy of +/- 0.5% (all analog front-end components). The Digital FCTR performs all other operations digitally and therefore has no accuracy errors after the AID and DIA conversions. The analog outputs of the FCTR are calibrated during the system-level calibration which includes the Quad Trip card and other components of the flow loop. In addition, the accuracy error introduced from the output 12-bit DIA converters is negligible when compared with other FCTR components. Therefore, the Digital FCTR card provides an accuracy of + 0.5%.
The temperature drift effects are not shown above because the FCTR application provides stable temperature operation. However, the combined effects of accuracy and temperature drift (over the rated 0-70 0C range of operation) are better than i 1%.
Steve Sawyer                                Leonid Sheikman GE Electronics & Technology                 GE Electronics. Technology 1112412003                                 1112412003

Attachment 7.7 Vermont Yankee Setpoint Control Program Interdepartmental Review of Calculation VYC-0693A Revision 2 VERMONT YANKEE SETPOINT CONTROL PROGRAM INTERDEPARTMENTAL REVIEW OF CALCULATION:
VYC- 693A Revision 2 has been prepared and independently reviewed. The Departments impacted by this calculation are requested to review the results of this calculation, concur with the results and/or recommendations, and document the department's acceptance prior to the calculation being approved.
: 1. Summarv         This calculation evaluates the uncertainty & setpoint for the APRM/RBM Neutron Monitoring Trip Loops.
: 2. Calculation Open Items:                                                      AP-0028 to be Assigned 2.1. None                                                                 NA
: 3. Department Review - contact the Setpoint Program Manager (Joe Garozzo) if not in agreement with the conclusions/statements.
3.1. Vermont Yankee I&C 3.1.a. Procedure OP-4308 will require the following:
: 1. Add the following in the procedure discussion:
Allowable Values:
AJlowable Values Output Instrument                                          % RxP           mV            Curve % RxP kPRM A, B, C, D, E, F Scram Trips ARTS/M1ELLLA Flow Biased APRM High Flux Scram (Two Loop Ops)
Core Flow 0 to < 3 1.1 % (point based on 25% flow)           71.1        5.6880         <0.4W+61.10%
Core Flow31.1 to <54.0 % (point based on 50 % flow)         97.31        7.7848        < 1.28W+33.31%
Core Flow 54.0 to <75 % (point based on 70% flow)          113.48        9.0784        < 0.66W+67.28%
Core Flow > 75%                                            116.96        9.3568              N/A AI'RM High Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)            68.09         5.4472        < 0.4W+58.09%
Core Flow 39.1 to <61.9 % (point based on 50% flow)         87.56         7.0048       < 1.28W+23.56%
Core Flow 61.9 to <83.0 % (point based on 70% flow)         108.3         8.6640       < 0.66W+62.10%
Core Flow> 83.0%                                            116.96        9.3568             N/A EPU Flow Biased APRM High Flux Scram (Two Loop Ops)
Core Flow 0 to <30.9 % (point based on 25% flow)             58.7        4.6960        < 0.33W+50.45%
Core Flow 30.9 to <66.7 % (point based on 50% flow)         80.73         6.4584       < 1.07W+27.23%
Core Flow 66.7 to <99.0 % (point based on 75% flow)        103.59         8.2872       < 0.55W+62.34%
Core Flow > 99.0%                                           116.96        9.3568             N/A APRMI H1igh Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)            56.25         4.5000       < 0.33W+48.00%
Core Flow 39.1 to <61.7 % (point based on 50% flow)         72.51         5.8008       < 1.07WV+19.01%
Core Flow 61.7 to <119.4 % (point based on 75% flow)        92.47         7.3976       < 0.55W+51.22%
Core Flow> 119.4%                                               116.96       9.3568 N/A Page        of 10

I      .   . .. .':. : '.Z Attachment 7.7 Vermont Yankee Setpoint Control Program Interdepartmental Review of Calculation VYC-0693A Revision 2
: a. As-Left and As-Found values:
Calibration Points, As-Left and As-Found Output Instrument                                         etting    s-Left As-Left    VYDC        VYDC
                                                                        'dc      Min        Max      As-Found As-Found Min         Max XPRM A, B, C, D, E, F Scram Trips ARTS/IMELLLA Flow Biased                                             _     _    ____l
               %.PRMHigh Flux Scram (Two Loop Ops)                                        l                     l
               -ore Flow 0 to < 31.1 % (point based on 25% flow)          5.5880 5.538         5.638      5.488      5.688 Core Flow 31.1 to <54.0 % (point based on 50 % flow)       7.6848 7.635         7.735      7.585      7.785 Core Flow 54.0 to <75 % (point based on 70% flow)          8.9784 8.928         9.028      8.8781     9.078 Core Flow> 75%                                             9.2568 9.207         9.307      9.157      9.357 APRM High Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)           5.3472 5.297         5.397      5.247      5.447 Core Flow 39.1 to <61.9 % (point based on 50% flow)        6.9048 6.855         6.955      6.805      7.005 Core Flow 61.9 to <83.0 % (point based on 70% flow)        8.564C 8.514         8.614      8.464      8.664 Core Flow > 83.0%                                          9.2568 9.207         9.307      9.157      9.357 EPU Flow Biased                                              _
kPRM High Flux Scram (Two Loop Ops)
               )w 0 to <30.9 % (point based on 25% flow)                  4.5960 4.546         4.646      4.496      4.696 Core Flow 30.9 to <66.7 % (point based on 50% flow)        6.3584 6.308         6.408      6.258      6.458 Core Flow 66.7 to <99.0 % (point based on 75% flow)        8.1872 8.137         8.237      8.087      8.287 Core Flow> 99.0%                                           9.2568 9.207         9.307      9.157      9.357 APRIMI High Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)           4.4000 4.350         4.450      4.3001     4.50C Core Flow 39.1 to <61.7 % (point based on 50% flow)        5.700     5.651      5.751      5.601       5.801 Core Flow 61.7 to <119.4 % (point based on 75%flow)        7.297     7.248      7.348      7.198      7.39E Core Flow> 11 9A%                                          9.2568 9.20          9.307      9.157       9.357 Note: Adjustment of the As Left Calibration Tolerance in the conservative direction is acceptable
: c. Revise Head to reflect: NA
: d. Insert the following M&TE requirements:
DMM's with total device error of better than +/-0.05% CS (10 VDC Range)
HP 3466A or the HP 34401A are acceptable devices to support this accuracy Requirements. VYC-1758 ...
: 2. In the body of the procedure and the data sheet revise as follows:
Page 2- of ID

. .  .                                 .  . . .: : . - -. . .    .. . .: :: .. : '. :. .: . 7' ..., -, .:  . , :, ::.:    ': : .:
Attachment 7.7 Vermont Yankee Setpoint Control Program Interdepartmental Review of Calculation VYC-0693A Revision 2
: b. Trip Setpoint:
Limiting Setpoints and Calibration Cardinal Points Output Instrument                                                 %RxP                       mV                 Curve %RxP APRM A, B, C, D, E, F Scram Trips ARTS/MiIELLLA Flow Biased APRM High Flux Scram (Two Loop Ops)
Core Flow 0 to <31.1 % (point based on 25% flow)                               69.85                 5.5880 < 0.4W+59.85%
Core Flow 31.1 to <54.0 % (point based on 50 % flow)                           96.0                  7.6848< 1.28W+32.06%
Core Flow 54.0 to <75 % (point based on 70% flow)                            112.2                   8.9784 < 0.66W+66.03%
Core Flow > 75%                                                              115.71                 9.2568 N/A APRM High Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)                               66.84                 5.3472 OAW+56.84%
Core Flow 39.1 to <61.9 % (point based on 50% flow)                            86.31                 6.9048< 1.28W+22.31%
Core Flow 61.9 to <83.0 % (point based on 70% flow)                          107.05                  8.5640 < 0.66NV+60.85%
Core Flow> 83.0%                                                             115.71                 9.2568 N/A EPU Flow Biased XPRM High Flux Scram (Two Loop Ops)
Core Flow 0 to <30.9 % (paint based on 25% flow)                               57.45                 4.5960 < 0.33W+49.20%
Core Flow 30.9 to <66.7 % (point based on 50% flow)                            79.4                  6.3584 < 1.07W+25.98%
Core Flow 66.7 to <99.0% (point based on 75% flow)                           102.3                   8.1872 <0.55W+61.09%
Core Flow> 99.0%                                                             115.71                 9.2568N/A.
APRMI 11igh Flux Scram (Single Loop Ops)
Core Flow 0 to <39.1 % (point based on 25% flow)                                        55           4.4000 < 0.33W+46.75%
Core Flow 39.1 to <61.7 % (point based on 50% flow)                            71.26                 5.7008 1.07W+17.76%
Core Flow 61.7 to <119.4 % (point based on 75% flow)                           91.22                 7.2976 < 0.55W+49.97%
Core Flow> 119.4%                                                             115.71                 9.2568 I/A
: c. Revise calibration data to reflect head correction of: NA
: d. Insert a 9-point calibration for all analog instruments: NAforNeutron Monitoring 3.1.b. The following comments/recommendations apply.
Concur                7
: l. Change Setpoints as identified above, PI/, b ?               '
Sign & Date Vermont Yankee I&C Representative
                           )k '6sct              I9A r4fey                   As           e     a            vi4I 9Of f/2c-//          f~cr1</#^i/7 rL Page .3 .. Of 10D

Attachment 7.7 Vermont Yankee Selpoint Control Program Interdepartmental Review of Calculation VYC-0693A. Revision 2 VERMONT YANKEE SETPOINT CONTROL PROGRAM INTERDEPARTMENTAL REVIEW OF CALCULATION:
VYC- 693A Revision 2 has been prepared and independently reviewed. The Departments impacted by this calculation are requested to review the results of this calculation, concur with the results and/or recomnmendations, and document the department's acceptance prior to the calculation being approved.
: 1. Summary:        This calculation evaluates the uncertainty & setpoint for the APRMRBM Neutron Monitoring Trip Loops.
: 2. Calculation Open Items:                                                     AP-0028 to be Assigned 2.1. None                                                                 NA
: 3. Department Review - contact the Setpoint Program Manager (Joe Garozzo) if not in agreement with the conclusions/statements.
3.2. Vermont Yankee Reactor Engineering Concur/
3.2.a. None 0! veel'/       st-0
: 1. Improved Technical Specifications                                                  \9.0 -c)C (e
Analytical Limits APRM Hig-h Flux Scram (Two Loot) Oss)
Core Flow 0 to <31.1 %                        < 0.4W+64.4%
Core Flow 31.1 to < 54.0 %                    < 1.28W+37.0%
Core Flow 54.0 to < 75 %                      < 0.66W+70.S%
Core Flow > 75%                               Maximum of 120%
APRM High Flux Scram (Single Loop Ops)                                           CcXNM-          I %~ C" CZT P hM Core Flow 0 to <39.1 %                        < 0.4W+61.2%                         to I-, %L %\tySs? ~1-rm Core Flow 39.1 to c 61.9 %                    < 1.28W+26.8%                        2zo'u TrO Lts-P.
Core Flow 61.9 to < 83.0 %                    < 0.66W+65.2%
Core Flow >83%                                Maximum of 120%
APRM High Flux Scram (Two Loop Ops)                                             OJOllc
((,'
Core Flow 0 to < 30.9 %                       < 0.33W+53.7%
Core Flow 30.9 to < 66.7 %                     < 1.07W+30.8%
Core Flow 66.7 to < 99 %                      < 0.55W+65.5%
Core Flow > 99%                               Maximum of 120%
APRM High Flux Scram (Single Loop Ops)
Core Flow 0 to < 39.1 %                        < 0.33W+51.1%
Core Flow 39.1 to < 61.7 %                     < 1.07W+22.2%
Core Flow 61.7 to < 119.4 %                    < 0.55W+54.3%
Core Flow >119.4                               Maximum of 120%
Sign & Date Zap\o IX 0k.                        /12t-1-03 Vermont Yankee RV, Representative Page     q   of Io

Attachment 7.7 Vermont Yankee Setpoint Control Program Interdepartmental Review of Calculation VYC-0693A Revision 2 VERMONT YANKEE SETPOINT CONTROL PROGRAM INTERDEPARTMENTAL REVIEW OF CALCULATION:
VYC- 693A Revision 2 has been prepared and independently reviewed. The Departments impacted by this calculation are requested to review the results of this calculation, concur with the results and/or recommendations, and document the department's acceptance prior to the calculation being approved.
: 1. Summarv.       This calculation evaluates the uncertainty & setpoint for the APRMIRBM Neutron Monitoring Trip Loops.
: 2. Calculation Open Items:                                                    AP-0028 to be Assianed 2.1. None                                                                  NA
: 3. Department Review - contact the Setpoint Program Manager (Joe Garozzo) if not in agreement with the conclusions/statements.
3.3. Vermont Yankee Operations Concur 3.3.a. Recahlbrate APRMs LPRM7 tc after seismic event Sign& Date                  Q.I         v           0F/0,/ja Vermont 'Yankee Operations Representative Page    A of 16

                                                                                      . ... .   . I:     . .
Attachment 7.7 Vermont Yankee Setpoint Control Program Interdepartmental Review of Calculation VYC-0693A Revision 2 VERMONT YANKEE SETPOINT CONTROL PROGRAM INTERDEPARTMENTAL REVIEW OF CALCULATION:
VYC- 693A Revision 2 has been prepared and independently reviewed. The Departments impacted by this calculation are requested to review the results of this calculation, concur with the results and/or recommendations, and document the department's acceptance prior to the calculation being approved.
: 1. Summary.       This calculation evaluates the uncertainty & setpoint for the APRM/RBM Neutron Monitoring Trip Loops.
: 2. Calculation Open Items:                                                    AP-0028 to be Assigned 2.1. None                                                                NA
: 3. Department Review - contact the Setpoint Program Manager (Joe Garozzo) if not in agreement with the conclusions/statements.
3.4. Vermont Yankee Systems Manager Concur       Comments 3.4.a. This analysis supports the design bases for the APRM!RBM Neutron Monitoring Trip System Sign&Date       .-        g                       / IZ t--Z0oe5 Ver     nt Yankee System Engineering Representative Page        4   of IC)

Program Yankee Setpoint Control Vermont Attachment 7.7 Attachmnent 7.7 Vermont Yankee Setpoint Control Program Interdepartmental Review of Calculation VYC-0693A Revision 2 Comments:
None Page 7 of 1 6

Calculation Number: VYC-693A             Revision Number:     2 CCN Number:N/A      Attachment    7.,s        pA68   s oF 1 DOCUMENTATION OF COMPUTER RESOURCE USE                                  Izb/a1s3 CALCULATION NO.:              VYC-0693A                    -
REVISION NO.:        2          CCN No.:_N/A Computer Used (include manufacturer, CPU Type, and operating system version and level):
Dell Dimension 8200 Pentium 4 2.4 MHz; Windows XP Professional version 5.1 service pack I Microsoft Excel version 2002 Service Pack 2._
Computer Input Attached*?       El Yes    l No LocationlIdentifier.
Computer Output Attached*?         a  Yes ED No Location/Identifier:
* Large   volume input/output should be provided on CD. See Appendix E for format requirements.
List the computer codes used, and complete the following:
Approved per      Appropriateness    Outstanding SPRs PP 7800           Verified         or Code Errorsi Code Name/Version and/or Script File                   Yes 3 _   No       Yes       No       Yes 2        No Calculation Detail and Charts                                    -t/                                       V (Attachments B1 through B4)
Microsoft Excel Version 2002 SR 2 I~~~                                                             I         I:
                                                                                             ~~~~~~~~
                                                       - =         =     +/- =        I =       +/-
1 Software    Problem Report (SPR), does not exist as a reporting method in PP 7800 and AP 6030. Contact          the Code sponsor and review any outstanding SPRs or Code errors. [ER2000805]
2 If yes, fill out information below.
3If yes, include the Code name on the Computer Code line of the title page, VYAPF 0017.01.
If a computer code was not verified in accordance with PP 7800 and AP 6030, or if there are outstanding SPRs, state below why it is appropriate.
Code Name/Script File                                   Appropriateness Calculation Detail and Charts (Attachments Appropriateness was verified Bl through B4) Microsoft Excel Version                        through hand calculation 2002 SR 2 I.     -           _~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

I Calculation Number: VYC-693A            Revision Number: 2    CCN Number: N/A            Attachment 7./
_4- t14t/13 Page O,/ 1 of J1a VY CALCULATION REVIEW FORM Calculation Number:        VYC-693A                       Revision Number:              2                    CCN Number:                       N/A

==Title:==
APRM/RBM Neutron Monitoring-Trip Loops Reviewer Assigned:.       Kirk Melson                             Required Date:
El INTERDISCIPLINE REVIEW                 E INDEPENDENT REVIEW COMMENTS*                                                                 RESOLUTION
: 1. Excel Sheets - For TLU terms, the inouts to the equation are          1. Made all ---
innut I--
terms in values which format to percent of
                                                                                                                                              -- I-------      - span.
                                                                                                                                                                 -I-mixed with some being listed in tenns of a decimal value and labeled as percent of span, and others formatted as percent of span. Need to express input terms the same.
: 2. Excel Sheets - For TLU terms, the inputs to the equation are          2. Changed input values to percent of Reactor Power.
mixed, in that some terms are actually in percent of span. and others are in percent Reactor Power. Need input terms to be consistent.
: 3. Either remove flow noise as a PMA term or provide specific             3. All uncertainties for flow are covered by VYC-690. Removed flow reference.                                                                noise as an uncertainty parameter with PMA.
: 4. Calibration tolerances for Fixed Hi Scram and Reduced Fixed            4. Corrected Cal Tolerances. based on OP-4308 and OP-43108.
Scram are different than for Flow Bias. Please revise, based on.
procedure.
: 5. Add input tables for Flow Values to Word Document.
: 5. Added Tables 8 and 9.
__ f      eA.     .. _/_     09/21/03               le&: "/-..         )I.                L.k-"                          / 09/21/03 Reviewer Signature                         Date                     Ca'lculation Preparer (Comments Resolved)                                     Date Method of Review:         0 Calculation/Analysis Review oAlternative Calculation                       '-              -                                        /_09/21/03_
ol Qualification Testing                          Reviewer Signature (Comments Resolved)                                          Date
*Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly.
VYAPF 0017.04 (Sample)
AP 0017 Rev. 8, LPC 2 Page 1 of 1

7 Calculation Number: VYC-693A            Revision Number: 2      CCN Number: N/A    Attachment     7./_
4Z1/63      Page _//     of _/J0 VY CALCULATION REVIEW FORM I Calculation Number:-       VYC-693A                         Revision Number:      2                CCN Number:             N/A

==Title:==
APRM/RBM Neutron Monitoring Trip Loops Reviewer Assigned:        Kirk Melson                                             Required Date:
El INTERDISCIPLINE REVIEW                 0    INDEPENDENT REVIEW COMMENTS*                                                                  RESOLUTION I
: 6. Correct Flow Break Points for ARTSIMELLLA Single Loop Ops               6. Corrected.
in Table 3 of Word document.
: 7. Chance AL from 13.5 to 15 in snreadsheets.                              7. Corrected to 15.
: 8. Correct cross references in Cells A25. A26. and El6 to reflect         8. Corrected cross references.
: 9. LPRM drift term is extrapolated from 700 hours to 1250 hours.           9. Extrapolation no longer performed. Drift for 700 hours is used.
which is no longer necessary. Please remove the extrapolation.
: 10. Remove APRM Avg Circuit and LPRM items from testing error.            10. Moved these errors to non-tested uncertainties.
I1. Remove Scientific notations in the spreadsheets.                      I 1. Corrected formatting to decimal.
: 12. Remove all equations. values for other than Method 1.                 12. Removed.
: 13. Set Cal Effect equal to Accuracv. as it is larger than CT.            13. Set equal to accuracv term.
: 14. Biases are negative, and the negative error is to be used for AV. 14. Showed bias in negative uncert comp and changed to use neg for AV.
Reviewer Signature
_  I    09/21/03 Date
                                                                    ' .Y - --s". xA        HO   . /,;.
{         I         _09/21/03 Calculation Preparer (Comments Resolved)             Date Method of Review:          El Calculation/Analysis Review o Alternative Calculation             _                   b9       7                  _ / 09/21/03 o Qualification Testing                            Reviewer Signature (Comments Resolved)                 Date
    *Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly.
VYAPF 0017.04 (Sample)
AP 0017 Rev. 8 LPC 2 Page 1 of 1

Docket No. 50-271 BVY 03-115 Attachment 3 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 257 Discussion of Changes for Revised Technical Specifications

BVY 03-115 I/Attachment 3 / Page I of 2 DISCUSSION OF CHANGES TO REVISED TECHNICAL SPECIFICATIONS TS 2.1 .A.1 .a (current page 6)
The heading of this section is changed from "APRM Flux Scram Trip Setting (Run Mode)" to "APRM Flux Scram Allowable Value (Run Mode)."
The Standard Technical Specifications nomenclature of "Allowable Value" is adopted for this trip function of the reactor protection system. This change is made to clarify that the specification is an Allowable Value that corresponds to the limiting value that the instrument may have for operability. This change is made to draw a distinction from other TS that may specify trip settings that differ from the definition of an Allowable Value. This change is acceptable because it represents the appropriate operability limitation for the parameter (Neutron Flux Trip Settings).
TS 2.1 A.l.a (current page 6)
The specification for this limiting safety system setting is changed from "When the mode switch is in the RUN position, the APRM flux scram trip setting shall be as shown on Figure 2.1.1 and shall be: S<0.66(W-AW)+54%" to "When the mode switch is in the RUN position, the APRM flux scram Allowable Value shall be:
Two loop operation:
S<       0.4 W + 61.10%           for       0% <Wc<       31.1%
S<      1.28 W + 33.31%           for 31.1% <W<           54.0%
S < 0.66 W + 67.28%               for 54.0% < W <         75.0%
with a maximum of 117.0% power for W > 75.0%
Single loop operation:
S<       0.4 W + 58.09%           for       0% <W<        39.1%
S<       1.28 W + 23.56%           for   39.1%    <W<      61.9%
S'< 0.66 W + 62.10%               for 61.9% < W <         83.0%
with a maximum of 117.0% power for W > 83.0%"
The change in the neutron flux trip setting algorithm is supported by the ARTS/MELLLA analysis provided as part of Proposed Change No. 257. The deletion of reference to TS Figure 2.1.1 is discussed below.
TS Figure 2.1.1 (current page 11)
TS Figure 2.1.1 does not provide any requirement not included in the stated algorithms for this function. Because the figure is redundant, it can be eliminated from TS without any change in technical requirements. In addition, elimination of this figure is consistent with Standard Technical Specifications.

BVY 03-115 / Attachment 3 / Page 2 of 2 TS Table 3.1.1 (current page 21)
Trip function no. 4, "APRM (APRM A-F) High Flux (flow bias)," is changed consistent with the algorithm change described above for TS 2.1.A.1.a. The algorithm specified in the "Trip Settings" column is changed to the Allowable Value algorithms resulting from the adoption of ARTS/MELLLA. In addition, Footnote (4) to Table 3.1.1 is changed to add a clarifying statement: "The specified APRM High Flux scram (flow bias) Trip Setting is an Allowable Value, which is the limiting value that the trip setpoint may have when tested periodically. The actual scram trip setting is conservatively set in relation to the Allowable Value." The change is made to emphasize that the specification is an Allowable Value that corresponds to the limiting value trip setpoint that the instrument have for operability. This change is made to draw a distinction from other TS that may specify trip settings that differ from the definition of an Allowable Value.
In addition, Footnote (4) is also modified to eliminate the statement: "AW is the difference between the two loop and single loop drive flow at the same core flow. This difference must be accounted for during single loop operation. AW = 0 for two recirculation loop operation." This statement can be eliminated because separate algorithm specifications are now provided for two loop and single recirculation loop operation, and the term "AW" has been eliminated from TS.
Bases Changes The TS Bases provide explanation and rationale for associated TS requirements, and in some cases, how they are to be implemented. Associated changes to the TS Bases are being made to conform to the changed TS and to add clarity to existing requirements. Bases do not establish actual requirements, and as such do not change technical requirements of the TS. The Bases changes are therefore acceptable, since they administratively document the reasons and provide additional understanding for the associated TS requirements.

Docket No. 50-271 BVY 03-115 Attachment 4 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 257 Replacement Mark-Ups of the Current Technical Specifications

VYNPS 1.1  SAFETY LIMIT                             2.1  LIMITING SAFETY SYSTEM SETTING 1.1  FUEL CLADDING INTEGRITY                   2.1 FUEL CLADDING INTEGRITY Applicability:                                Applicability:
Applies to the interrelated variable          Applies to trip setting of the associated with fuel thermal                  instruments and devices which are behavior.                                     provided to prevent the nuclear system safety limits from being exceeded.
Objective:                                    Objective:
To establish limits below which the           To define the level of the process integrity of the fuel cladding is             variable at which automatic preserved.                                    protective action is initiated.
Specification:
Specification:
A. Trip Settings A. Bundle Safety Limit (Reactor Pressure >800 psia and Core Flow              The limiting safety system trip
         >10% of Rated)                                settings shall be as specified below:
When the reactor pressure is
         >800 psia and the core flow is                1. Neutron Flux Trip Settings greater than 10% of rated:
: a. APRM Flux ScramR
: 1. A Minimum Critical Power                                       (Run Mode)
I           Ratio (MCPR) of less than 1.10 (1.12 for Single Loop                          When the mode switch iLs I           Operation) shall constitute                         in the RUN position, I:he violation of the Fuel                                  APRMf~uxscram     i Cladding Integrity Safety                                sett6ghal Heas Limit (FCISL).                                          sonon Fissue 2.1.1 I                                                       -w,  N.,a,,Ma+/-+/- De:
(
S  = setting in percent of RT#1                                                    rated thermal power (1593 MWt)
W  - percent rated two loop drive flow where 100%
rated drive flow is that flow equivalent to 48 x 10l lbs/hr core flow Amendment No. 4&, 4., 44, .94, .4, 4-4, 4-64, 449, 176                             6

VYNPS
                                           -        APRM Setpoints shall be <
on the graph.
20                                     80 100 For single loop operation, the APRM Scram setting is adjusted according to Technical Specification 2.1.A.1.a Amendment No. G,   .94, l 8    211 27,                                     11

VYNPS BASES:
t  llowable Value   >
2.1   FUEL CLADDING INTEGRITY A. Trip Settings The bases for individual trip settings are discussed in the following paragraphs.
: 1. Neutron Flux Trip Settings
: a. APRM Flux Scram                   Run Mode)
The average power range monitoring (APRM) system, which is calibrated using heat balance data taken during steady state conditions, reads in percent of rated thermal power (1593 MWt). Because fission chambers provide the basic input signals, the APRM system responds directly to average neutron flux. During transients, the instantaneous rate of heat transfer from the fuel (reactor thermal power) is less than the instantaneous neutron flux due to the time constant Csetting   wof    the fuel. Therefore, during abnormal operational sients, the thermal power of the fuel will be less than that      *!N~cated by the neutron flux at the scram setting.
Analyses ar        formed to demonstrate that the APRM flux scram over the            f settings from a maximum of 120% to the minimum flow bias                       provide protection from the fuel safety limit or a       a ormal operational transients including those that may result in a thermal hydraulic instability.
An increase in the APRM scram trip setting would decrease the margin present before the fuel cladding integrity Safety Limit is reached. The APRM scram trip setting was determined by an analysis of margins required to provide a reasonable range for maneuvering during operation. Reducing this operating margin would increase the frequency of spurious scrams which have an adverse effect on reactor safety because of the resulting thermal stresses. Thus, the
    *INSERT #2>           APRM scram trip setting was selected because it provides adequate margin for the fuel cladding integrity Safety Limit yet allows operating margin that reduces the possibility of
               \         ~~unnecessary   scrams.*
The scram tr esetting must be ad jsted to ensure          at the LHGR transi     t peak is not incr sed for any co *nation of
<INSERT #3>               MFLPD an reactor core therma power. If the s am requires a chan     due to an abnormal eating condition it will be acco pished by increasing he APRM gain by           e ratio in Spe ification 2.1.A.l.a, hus assuring a rector scram at Seerthan de      ove
* s     For single recirculation loop operation, the APRH flux scram trip setting is reduced in accordance with the analysis presented in NEDO-30060, February 1983. This adjustment accounts for the difference between the single loop and two loop drive flow at the same core flow, and ensures that the margin of safety is not reduced during single loop operation.
Analyses of the limiting transients show that no scram adjustment is required to assure fuel cladding integrity when the transient is initiated from the operating limit MCPR defined in the Core Operating Limits Report.
AN, 4<INSERT #4>
Amendment No. i@-, id        +9, 4>, Ad, 8-4,  Ail44,                                   14

VYNPS TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT REQUIREMENTS Required Modes in Which Functions Mlust                   ACTIONS When be Operating          Minimum Number      Minimum Operating    Conditions For Instrument       Operation Channels Per       Are Not Trip Function           Trip Settings     Refuel (1)     Startup (12)  Run Trip System (2)  Satisfied (3)
: 1. Mode Switch in                                    X              X        X          1                A Shutdown (5A-Sl)
: 2. Manual Scram                                      X              X        X          1                A (SA-S3A/B)
: 3. IRM (7-41(A-F))
High Flux               <120/125                  X             X                    2                A INOP                                              X             x                    2                A
: 4. APRM (APRM A-F)
High Flux                                                                 X          2             A or B (flow bias)
I High Flux (reduced)     <15%                      X             X                    2                A INOP                                                                      X        2 (5)           A or B
: 5. High Reactor            <1055 psig                X             X         X          2               A Pressure (PT-2-3-5S(A-D)(M))
: 6. High Drywell            c2.5 psig                X              X         X          2               A Pressure (PT-5-12(A-D)(M))
: 7. Reactor Low (6)         >127.0 inches            x              x         X          2               A Water Level (LT-2-3-57A/B(M))
(LT-2-3-58A/B(M))
: 8. Scram Discharge         <21 gallons              X              X         X          2               A Volume High Level                                                              (per volume)
(LT-3-231 (A-H) (M))
Amendment No. G,    44,  4, S",   6, a14, -9, 44, 94-, 4l64, -1G,18 7                                             21

VYNPS TABLE 3.1.1 NOTES (Cont'd)
: 3. When the requirements in the column "Minimum Number of Operating Instrument Channels Per Trip System' cannot be met for one system, that system shall be tripped. If the requirements cannot be met for both trip systems, the appropriate ACTIONS listed below shall be taken:
_iate insertion of operable rods and complete insertion of all
<INSERT#6>          able rods within four hours.
               - -uuce power level to IRM range and place mode switch in the "Startup/Hot Standby" position within eight hours.
c)    Reduce turbine load and close main steam line isolation valves within 8 hours.
d)    Reduce reactor power to less than 30% of rated within 8 hours.
: 4.    "WI' is percent rated two loop drive flow where 100l rated drive flow is that flow equivalent to 48 x 106 lbs/hr core flow. AW is he differenc                  etween e two loop    d single loop d ve flow at the sa           core flow,       is difference ust be accounte           or during single   op operation        AW     0 for /
two rec culation loop op ation.
: 5. To be considered operable an APRM must have at least 2 LPRM inputs per level and at least a total of 13 LPRM inputs, except that channels A, C, D, and F may lose all LPRM inputs from the companion APRM Cabinet plus one additional LPRM input and still    be considered operable.
: 6. The top of the enriched fuel has been designated as 0 inches and provides common reference level for all vessel water level instrumentation.
: 7. Deleted.
: 8. Deleted.
: 9. Channel signals for the turbine control valve fast closure trip shall be derived from the same event or events which cause the control valve fast closure.
: 10. Turbine stop valve closure and turbine control valve fast closure scram signals may be bypassed at <30% of reactor Rated Thermal Power.
: 11. Not used.
: 12. While performing refuel interlock checks which require the mode switch to be in Startup, the reduced APRM high flux scram need not be operable provided:
: a. The following trip functions are operable:
: 1. Mode switch in shutdown,
: 2. Manual scram,
: 3. High flux IRM scram
: 4. High flux SRM scram in noncoincidence,
: 5. Scram discharge volume high water level, and;
: b. No more than two (2) control rods withdrawn. The two (2) control rods that can be withdrawn cannot be face adjacent or diagonally adjacent.
Amendment No.     '4, Go,  G, 644, 46&, 4,    94, 94, 4i44, 74-3-, 4-4, 4-94, 212            24

INSERT #1 Two loop operation:
S<        0.4W + 61.10%          for       0% <W< 31.1%
S<      1.28W + 33.31%           for 31.1% <W< 54.0%
S < 0.66 W + 67.28%              for   54.0% < W < 75.0%
with a maximum of 117.0% power for W > 75.0%
Single loop operation:
S<        0.4 W + 58.09%         for       0% <W< 39.1%
S<      1.28 W + 23.56%          for   39.1% <W< 61.9%
S<      0.66 W + 62.10%          for   61.9% < W < 83.0%
with a maximum of 117.0% power for W > 83.0%
INSERT #2 The relationship between recirculation drive flow and reactor core flow is non-linear at low core flows. Due to stability concerns, separate APRM flow biased scram trip setting equations are provided for low core flows.
INSERT #3 The APRM flow biased flux scram Allowable Value is the limiting value that the trip setpoint may have when tested periodically, beyond which appropriate action shall be taken. For Vermont Yankee, the periodic testing is defined as the calibration. The actual scram trip is conservatively set in relation to the Allowable Value to ensure operability between periodic testing.
INSERT #4 The single loop operation equations are based on a bounding (maximum) difference between two loop and single loop drive flow at the same core flow of 8%.

INSERT #5 Two loop operation: (4)
S<       0.4 W + 61.10%            for      0% <W< 31.1%
S<      1.28 W + 33.31%            for 31.1% <W< 54.0%
S < 0.66 W + 67.28%                for 54.0% < W < 75.0%
with a maximum of 117.0% power for W > 75.0%
Single loop operation: (4)
S<       0.4 W +       58.09%      for      0%    <V W<     39.1%
S<      1.28 W + 23.56%            for 39.1% <W< 61.9%
S<      0.66W + 62.10%             for 61.9% <W< 83.0%
with a maximum of 117.0% power for W > 83.0%
INSERT #6 The specified APRM High Flux scram (flow bias) Trip Setting is an Allowable Value, which is the limiting value that the trip setpoint may have when tested periodically. The actual scram trip setting is conservatively set in relation to the Allowable Value.

Docket No. 50-271 BVY 03-1 15 Attachment 5 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 257 Replacement Re-typed Technical Specifications Pages

VYNPS 1.1  SAFETY LIMIT                              2.1    LIMITING SAFETY SYSTEM SETTING 1.1  FUEL CLADDING INTEGRITY                   2.1    FUEL CLADDING INTEGRITY Applicability:                                   Applicability:
Applies to the interrelated                      Applies to trip setting of the variable associated with fuel                    instruments and devices which are thermal behavior.                                provided to prevent the nuclear system safety limits from being exceeded.
Objective:                                       Objective:
To establish limits below which                  To define the level of the process the integrity of the fuel                        variable at which automatic cladding is preserved.                           protective action is initiated.
Specification:
Specification:
A. Trip Settings A. Bundle Safety Limit (Reactor Pressure >800 psia and Core                       The limiting safety system Flow >10% of Rated)                               trip settings shall be as specified below:
When the reactor pressure is
          >800 psia and the core flow is                    1. Neutron Flux Trip Settings greater than 10% of rated:
: a. APRM Flux Scram
: 1. A Minimum Critical Power                                Allowable Value            I Ratio (MCPR) of less than                                (Run Mode) 1.10 (1.12 for Single Loop Operation) shall constitute                             When the mode switch violation of the Fuel                                   is in the RUN Cladding Integrity Safety                               position, the APRM Limit (FCISL).                                          flux scram Allowable Value shall be:            I Two loop operation:
SS 0.4W+ 61.10% for      0% < W
* 31.1%
SS 1.28W+ 33.31% for 31.1% < W S 54.0%
SS 0.66W+ 67.28% for 54.0% < W
* 75.0%
With a maximum of 117.0% power for W >
75.0%
Single loop operation:
SS 0.4W+ 58.09% for      0% < W
* 39.1%
SS 1.28W+ 23.56% for 39.1% < W
* 61.9%
SS 0.66W+ 62.10% for 61.9% < W
* 83.0%
With a maximum of 117.0% power for W >
83.0%
where:
S  = setting in percent of rated thermal power (1593 MWt)
Amendment No. 14-, 4-, 44, .9, .94, 4G9, 4S4,  l-5-9, 4-76                                   6

VYNPS Amendment No. 14, 94, 8, 24111       11

VYNPS BASES:
2.1   FUEL CLADDING INTEGRITY A. Trip Settings The bases for individual trip settings are discussed in the following paragraphs.
: 1. Neutron Flux Trip Settings
: a. APRM Flux Scram Allowable Value (Run Mode)
The average power range monitoring (APRM) system, which is calibrated using heat balance data taken during steady state conditions, reads in percent of rated thermal power (1593 MWt). Because fission chambers provide the basic input signals, the APRM system responds directly to average neutron flux. During transients, the instantaneous rate of heat transfer from the fuel (reactor thermal power) is less than the instantaneous neutron flux due to the time constant of the fuel. Therefore, during abnormal operational transients, the thermal power of the fuel will be less than that indicated by the neutron flux at the scram setting.
Analyses are performed to demonstrate that the APRM flux scram over the range of settings from a maximum of 120t to the minimum flow biased setting provide protection from the fuel safety limit for all abnormal operational transients including those that may result in a thermal hydraulic instability.
An increase in the APRM scram trip setting would decrease the margin present before the fuel cladding integrity Safety Limit is reached. The APRM scram trip setting was determined by an analysis of margins required to provide a reasonable range for maneuvering during operation. Reducing this operating margin would increase the frequency of spurious scrams which have an adverse effect on reactor safety because of the resulting thermal stresses. Thus, the APRM scram trip setting was selected because it provides adequate margin for the fuel cladding integrity Safety Limit yet allows operating margin that reduces the possibility of unnecessary scrams. The relationship between recirculation drive flow and reactor core flow is non-linear at low core flows. Due to stability concerns, separate APRM flow biased scram trip setting equations are provided for low core flows.
The APRM flow biased flux scram Allowable Value is the limiting value that the trip setpoint may have when tested periodically, beyond which appropriate action shall be taken. For Vermont Yankee, the periodic testing is defined as the calibration. The actual scram trip is conservatively set in relation to the Allowable Value to ensure operability between periodic testing. For single recirculation loop operation, the APRM flux scram trip setting is reduced in accordance with the analysis presented in NEDO-30060, February 1983. This adjustment accounts for the difference between the single loop and two loop drive flow at the same core flow, and ensures that the margin of safety is not reduced during single loop operation. The single loop Amendment No. 4A, aS,   347,4-% S-1, 94, a4-G,   A4                             16 14

VYNPS BASES:   2.1  (Cont'd) operation equations are based on a bounding (maximum) difference between two loop and single loop drive flow at the same core flow of 8%.
Analyses of the limiting transients show that no scram adjustment is required to assure fuel cladding integrity when the transient is initiated from the operating limit MCPR defined in the Core Operating Limits Report.
Amendment No.                                                              14a

VYNPS TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT REQUIREMENTS Required ACTIONS When Modes in Which           Minimum Number     Minimum Functions Must be Operatiirig      Operating      Conditions Instrument   For Operation Channels Per     Are Not Trip Function                    Trip Settings                    Refuel (1)     Startup(12)    Run  Trip System (2) Satisfied (3)
: 1. Mode Switch in Shutdown (SA-Sl)                                                       X             X           X          1              A
: 2. Manual Scram                                                           X             x           x          1              A (SA-S3A/B)
: 3. IRM (7-41(A-F))
High Flux                          <120/125                            X             X                      2              A INOP                                                              X             X                     2               A
: 4. APRM (APRM A-F)
High Flux           Two loop operation:     (4)                                                   X         2           A or B (flow bias)        S5 0.4W+ 61.10% for     0% < W S 31.1%
SS 1.28W+ 33.31% for 31.1% < W S 54.0%
SS 0.66W+ 67.28% for 54.0% < W S 75.0%
With a maximum of 117.0% power for W > 75.0V Single loop operation:      (4)
SS 0.4W+ 58.09% for     0% < W S 39.1%
SS 1.28W+ 23.56% for 39.1% < W S 61.9%
SS 0.66W+ 62.10% for 61.9% < W 5 83.0%
With a maximum of 117.0% power for W > 83.0%
High Flux                             <15%                             X             X                      2              A (reduced)
INOP                                                                                X            X       2(5)          A or B
: 5. High Reactor                      <1055 psig                           X             X            X         2              A Pressure (PT-2-3-55(A-D)
(M)
Amendment No.      , 44, 44,    68,  47, 48, 44,  94,  94,   l46,    -84,    182                                                  21

VYNPS TABLE 3.1.1 NOTES (Cont'd)
: 3. When the requirements in the column "Minimum Number of Operating Instrument Channels Per Trip System" cannot be met for one system, that system shall be tripped. If the requirements cannot be met for both trip systems, the appropriate ACTIONS listed below shall be taken:
a)   Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
b)    Reduce power level to IRM range and place mode switch in the "Startup/Hot Standby" position within eight hours.
c)   Reduce turbine load and close main steam line isolation valves within 8 hours.
d)  Reduce reactor power to less than 30t of rated within 8 hours.
: 4. The specified APRM High Flux scram (flow bias) Trip Setting is an Allowable Value, which is the limiting value that the trip setpoint may have when tested periodically. The actual scram trip setting is conservatively set in relation to the Allowable Value. "W" is percent rated two loop drive flow where 100% rated drive flow is that flow equivalent to 48 x 106 lbs/hr core flow.
: 5. To be considered operable an APRM must have at least 2 LPRM inputs per level and at least a total of 13 LPRM inputs, except that channels A, C, D, and F may lose all LPRM inputs from the companion APRM Cabinet plus one additional LPRM input and still be considered operable.
: 6. The top of the enriched fuel has been designated as 0 inches and provides common reference level for all vessel water level instrumentation.
: 7. Deleted.
: 8. Deleted.
: 9. Channel signals for the turbine control valve fast closure trip shall be derived from the same event or events which cause the control valve fast closure.
: 10. Turbine stop valve closure and turbine control valve fast closure scram signals may be bypassed at <30% of reactor Rated Thermal Power.
: 11. Not used.
: 12. While performing refuel interlock checks which require the mode switch to be in Startup, the reduced APRM high flux scram need not be operable provided:
: a. The following trip functions are operable:
: 1. Mode switch in shutdown,
: 2. Manual scram,
: 3. High flux IRM scram
: 4. High flux SRM scram in noncoincidence,
: 5. Scram discharge volume high water level, and;
: b. No more than two (2) control rods withdrawn. The two (2) control rods that can be withdrawn cannot be face adjacent or diagonally adjacent.
Amendment No. -14,     , Ql,  64, A6s, -A, 9G, 894, -4, 4-, a4 , 4o, 2122          24}}