ML062200402
| ML062200402 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/02/2006 |
| From: | Costello L, Franklin M, Parry B Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-I/INST-1010, Rev 3 | |
| Download: ML062200402 (124) | |
Text
{{#Wiki_filter:Attachment 5 to SERIAL: HNP-06-089 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT HNP CALCULATION NO. HNP-I/INST-1010 HNP CALCULATION NO. HNP-I/INST-1010 Page A5-1 of 124
VSTStEZ 0 1080, 1090 CALC. TYPE DD CATEGORY CAROLINA POWER & LIGHT COMPANY CALCULATION NO. HNP-I/INST-1D10 FOR EVALUATION OF TECH SPEC RELATED SETPOINTS, ALLOWABLE VALUES, AND UNCERTAINTIES ASSOCIATED WITH RTS/ESFAS FUNCTIONS FOR STEAM GENERATOR REPLACEMENT (WITH CURRENT 2787 MWT-NSSS POWER OR UPRATE TO 2912.4 MWT-NSSS POWER) FOR SHEARON HARMIS NUCLEAR POWER PLANT NUCLEAR ENGINEERING DEPARTMENT QUALITY CLASS: MA r3 D r3c DOD Drz RESPONSIBLE X DESIGN VERIFIED BY APPROVED BY ENGINEER [ ENGINEERING REVIEW BY RESPONSIBLE SUPERVISOR DATE DATE DATE R.J. Phillips C.R. Fletcher Tony Groblewski 8/31/2000 8/31/2000 9/12/00 Brian Parry Chris Georgeson Ron Varner 2/23/02 2/27/02 3/13/02 REASON FOR- CHANGE: Incorporate Changes per ESR 99-00466 RO and ESR 00-00262 R3. i 2 Brian Parry Larry Costello Mike Franklin
- 518104 1 10/30/04 11/1/04 REASON FOR CHANGE: Incorporate Changes per EC # 56523 RO. AA 3 'rian Parry Larry Costello4 (CC3Z Mike Franklin V A REASO. FOR AN~ nco11/15/04 1 Change s I____59631__0.
REASON FOR CHANGE: Incorporate CManges per BC # 59631 RO.
CALCULATION NO. RUW-1I1NST-101O PAGE REV. 3 LIST OF EFFECTIVE PAGES
CALCULATION NO. .HNP-X/XNST-2.O10 PAGE ii REV. 3 LIST OF EFFECTIVE PAGES (Cont'd)
CALCULATION NO. HNP-I/INST-1010 PAGE iii REV. 0 TABLE OF CONTENTS Page No. List of Effective Pages ............... .................... .............. i - i Table of Contents ................. .................................... woo i - iv 1.0 ptRPOSE o.................... .*oo ... oo............................. 1 - 2 1.1 Objective and Applicability ..... ...... ....... ................... .1 1,2 Functional and Operational Description ............................ 1 1.3 Additional Background w...... ................... .. . 0. ... 1 - 2 2.0 LIST OF REFEPRENES ............... .................................. 2 - 6 3.0 BODY OF CALCULATION .................... .. o..o,.,..*.... I ............ 6 -12 3.1 Current Engineering/Licensing Basis Methodology ......... 6 - 7 3.2 Inputs and Assumptions .......... .......................... . 7 -10 3.3 Calculation Synopsis .- o............ ............... *... ...... 10 - 12
4.0 CONCLUSION
S .................... *..................................... 12 - 13 4.1 Channel Statistical Allowance (CSA) Results ............. o....... 12 4.2 Summary of wFive-Column" Tech Spec Terms ..................... 12 - 13 FIGURE I Channel Uncertainty Components Relative to Safety Analysis Limit, Allowable Value, and Trip Setpoint ..................... 14 FIGURE 2 Operating Conditions, Uncertainties, and Margins Relative to Safety Analysis Limit, Allowable Value, and Trip Setpoint ..... 15 TABLE 1-1 Suimary of General Equations/Relationships used in Report PCQL-355 Format ....... *0................................. 16 TABLE 1-2 Summary of General Equations/Relationships used for the Updated 'Five-Column" Tech Spec Format ...................... 17 - 18 TABLE 2-1 Excerpt of WCAP-15249 (Rev. 0), Table 3-21 [ENP RTS/ESFAS Channel Uncertainty Allowances] ............... 19 TABLE 2-2 PUR/SGR-Related Changes to RTS Setpoints and Analytical Limits .................. o ......... .......... . 20 - 21 TABLE 2-3 PUR/SGR-Related Changes to ESFAS Setpoints and Analytical Limits ...... ...oo .................................. 22 - 23
CALCULATION NO. MNP-IIXNST-1010 PAGE iv REV. 3 TABLE OF CONTENTS (Cont'd) TABLE 3-0 - Summary of CSA and Five-Column Tech Spec Terms Index of Calculation Summary Tables ........ .......... 24 - 25 TABLES 3-13 through 3 Summary of CSA and Five-Column Tech Spec Terms [for each RTS/ESFAS Function] ................................ 26 - 84 TABLE 4-1 - Tech Spec Table 2.2-1 Mark-up of Reactor Trip System Functions for PURISGR ........................................ 85 - 91 TABLE 4-2 - Tech Spec Table 3.3-4 Mark-up of ESP Actuation System Functions for PUR/SGR ........... *............................. 92 - 100 TABLE 4-3 - Sum=ary of RTS/ESFAS "Five-Columnw Terms for Post-PUR/SGR Operation ....... ...... o .......... 101 - 103 ATTACHMENTS Attachment Al - Calculation Design Verification Record of Lead Reviews .................................... (5 Pages) I Attachment A2 - Calculation Design Verification Record of Concurrent Review ................ . ....... (3 Pages) Attachment A3 - Calculation Indexing Table ............................. (6 Pages)
CALCULATION NO. HNP-X/INST-lDl0 PAGE 1 REV. 0 1.0 PURPOSE 1.1 Objective and Applicability This calculation documents the basis for 'final' values specified in MP Tech-nical Specification Tables 2.2-1 and 3.3-4 [References 2.1 and 2.21, as a re-sult of steam generator replacement [SCR] and/or power uprate [PURl projects implementation. It serves to reconcile values shown in other documents pro-duced for these projects, and to clarify determinationslspecification of such values within these Tech Spec Tables for post-SGR/PUR operation. 1.2 Functional and Operational Description Tech Spec RTS/ESFAS Trip Setpoint Tables [References 2.1 and 2.23 and their associated Bases define limLting safety system settings [LSSSI and operability limits for Reactor Trip System [RTS] and Engineered Safety Features Actuation Systems [ESFAS] functions. Various instrumentation channel surveillances [e.g., channel calibrations and functional checks per MSTs and LPs] are performed to demonstrate compliance with these RTS/ESFAS Tech Spec requirements. Acceptance criterion for these surveillances are generally defined within corresponding instrumentation channel scaling calculations (or electrical calculations, for RTS/ESFAS-related relay settings); scaling calculations, as revised for SGRIPUR implementation, should reflect the conclusions documented herein. 1.3 Additional Background Original engineering methodology and operability determination bases, for values defined in the Tech Spec RTS/ESFAS Trip Setpoint Tables, were contained in Westinghouse Letter Report FCQL-355 [Reference 2.3]. This methodology has been described as a "five-columna Tech Spec format. Its original intent was to minimize the number of licensing event reports (LERs) issued for inoperable instrumentation channels. The need for LER issuance was further reduced by NRC changes to 10CRF50.73 in 1983; reportability was only required if a loss of safety function occurred (versus the loss of a single channel). Tech Spec-related RTS/ZSFAS trip functions have also been defined within various site calculations (as listed within Reference 2.4 documentation]. Additionally, RUP FSAR Section 1.8 specifies a licensing commitment to RG 1.105, Rev. 1 [Reference 2.51. Subsequent industry guidance was provided by XSA Standard 667.04 [Reference 2.6] and by RG 1.105 [as recently updated per Rev. 3 (dated 12/99)]. NGGC procedural guidance (per Reference 2.7) allows for the use of vendor-prepared calculations which comply with newly-updated ISA calculational methodology and/or maintain consistency with current licensing bases. Westinghouse SGR/PUR-related evaluation of RTS/ESFAS trip functions was per-formed and documented by WCAP-15249 [Reference 2.8] and various supporting Westinghouse uncertainty calculations [listed within Reference 2.9 documenta-tion]. (This methodology has been described as a "two-columnw Tech Spec for-mat, which consists of the Trip Setpoint and the Allowable Value.) in gener-al, this evaluation process was intended to update original methodology/bases to more current industry practices (with respect to a more standardized Tech Spec format, as well as an updated treatment of measurement uncertainties [relative to notifications listed by Reference 2.111). For reference pur-poses, correspondence listed per Reference 2.12 acknowledges CP&L design
CALCULATION NO. HNP-I/INST-1010 PAGE 2 REV. 2 inputs (provided to Westinghouse) and other Westinghouse analysis inputs (specific for the MNP PURISGR projects) as noted within the Reference 2.10 listing. Owing to the existing 3We licensing bases, the Tech Spec RTS/ESFAS Trip Setpoint Tables will be retained in their original "five-colunnw format. By retaining the existing HNP licensing bases, the current plant controls (for channel calibrations/surveillances and for operability determinations) can be maintained for the PUR/SGR implementation. In most cases (i.e., except for steam generator [SG] narrow-range [N-R] level, Overtemperature /Overpower AT [OTAT/OPAT] trip channels) the instrument channels are physically (and/or analytically [by nominal setpoints and safety analysis limits]) unchanged, for PUR/SGR implementation, from their current plant operational and design requirements. Therefore, the current (pre-PUR/SGR) Tech Spec values shall be compared to those values computed herein, to evaluate the continued acceptability of current Tech Spec values (for post-PUR/SGR operation). Furthermore, it can be concluded that existing Tech Spec term values shall continue to apply for all channels, unless a specific technical justification requires the modification of Tech Spec term values. 2.0 LIST OF REFERENCES
- 1. 3WP Technical Specification Table 2.2-1, "Reactor Trip System Instrumen-tation Trip Setpointsu [mark-up included in Table 4-1 herein].
- 2. MNP Technical Specification Table 3.3-4, "Engineered Safety Features Actuation System Instrumentation Trip Setpoints" [mark-up included in Table 4-2 herein].
- 3. Westinghouse Letter Report FCQL-355, Rev. 1, dated July 1985, "Westinghouse Setpoint Methodology for Protection Systems, Shearon Harris" [J2DRAC 1364-053067, Rev. 3 contains the current revision of this methodology, at the time of issuance of this calculation].
- 4. IMP Calculations (associated with RTS/ESFAS trip functions]:
- a. HNP-I/INST-1002, Rev. 1, 'Reactor Coolant Loss of Flow Error Analysis".
- b. RNP-Z/ZNST-1003, Rev. 2, "Pressurizer Pressure Protection Error Analysis (Loops P-455, P-456, P-457)w.
- c. IMP-X/XNST-1030, Rev. 1, 'Refueling Water Storage Tank Level Accuracy Calculation / L-990, L-991, L-992, L-993 for Shearon Harris zOP Setpoints / HESS X&C".
- d. HNP-Z/INST-1045, Rev. 1, "Steam Generator Narrow Range Level: Low, Low-Low, and High-High Setpoints/Setpoint Aecuracy Calculation; L-473 through L-476, L-483 through L-486, and L-403 through L-4960.
NOTE: Bechtel-generated revision [Rev. 1C, dated 4/11/00] of MWP-V/INST-1045 has been prepared in support of the SO Replace-ment Project [as transmitted by Bechtel project letter SH/2000-029].
- e. HNP-XIZNST-1049, Rev. 0, "Replacement of RCS Narrow Range RTDs:
Acceptability Calculation; TE-412BI, 412B2, 412B3, 422BI, 422B2, 422B3, 432B1, 432B2, 432B3, 412D, 422D, 432bo.
- f. HNP-Z/ZNST-1054, Rev. 1, 'Turbine Throttle Valve Closure Uncertainty and Scaling Calculation".
CALCULATION NO. HNP-I/INST-1010 PAGE 3 REV. 0
- g. RNP-X/ZINST-1055, Rev. 0, 'Turbine Low Hydraulic Pressure Trip Uncertainty and Scaling Calculation'.
- h. EQS-2, Rev. 6, "Refueling Water Storage Tank Level SetpointO.
I. E2-0010, Rev. 5, 'Undervoltage Relays: Reactor Coolant Pump Motors IA, IB & IC-. jo Z2-0011, Rev. 4, "Underfrequency Relays: Reactor Coolant Pump Motors 1A, IB & IC-.
- k. E2-0005.09, Rev. 1, "Degraded Grid Voltage Protection for 6.9KV busses IA-SA & 1B-SB".
- 1. 0054-3RG, Rev. 2, "PSB-1 Loss of Offsite Power Relay SettingsO.
S. NRC Regulatory Guide 1.105, "Instrument Setpoints For Safety Related Systems". NOTE: FSAR Section 1.8 states IINP commitment to Rev. I of this RG; current version of RG is Rev. 3 (issued 12/99).
- 6. ISA Standard S67.04, Part 1, 1994, "Setpoints for Nuclear Safety-Related Instrumentation".
- 7. CP&L Procedure EGR-NGGC-0153, Rev. 7, "Engineering Instrument Setpoints*
- 8. WCAP-15249, Rev. 0, dated April 2000, "Westinghouse Protection System Setpoint Methodology for Harris Nuclear Plant (for Uprate to 2912.4 MWT -
NSSS Power and Replacement Steam Generators)" (designated as Westing-house Proprietary Class 2C; transmitted by project letter CQL-00-141].
- 9. Westinghouse Calculation Notes lassociated with RTS/ESFAS setpoint uncer-tainties]; designated as Westinghouse Proprietary Class 2:
- a. CN-TSS-98-19, Rev. 2, dated 3/99, "Harris (CQL) Control/Protection Uncertainty and Setpoint Analysis for Delta-75 Replacement Steam Generators (RSG) and Uprate to 2912.4 MWt-NSSS Power" [transmitted to CP&L by Bechtel project letter SH198-067].
- b. CN-TSS-98-33, Rev. 1, dated 9/13/99, "Harris (CQL) Overtemperature and Overpower Delta-T Reactor Trip Setpoints for Uprate to 2912.4 Xwt-NSSS Power" [transmitted by project letter CQL-99-0883.
Co CN-SSO-99-03, Rev. 1, dated 9/17/99, 'Harris (CQL) Pressurizer Pres-sure - Low Reactor Trip, Pressurizer Pressure - High Reactor Trip, Pressurizer Pressure - Low Safety Injection and P-1U Permissive Set-points for Uprate to 2912.4 Mwt - NSSS Power" [transmitted by project letter CQL-99-092].
- d. CN-SSO-99-5, Rev. 1, dated 9/7/99, 'Pressurizer Water Level - High Reactor Trip Setpoint Uncertainty Calculation for Harris Uprate to 2912.4 MWt, NSSS Power" (transmitted by project letter CQL-99-084).
- e. CN-SSO-99-7, Rev. 1, dated 9/21/99, "Harris Steamline Pressure-Low and Negative Steamline Pressure Rate-High Technical Specification Setpoint for tprate to 2912.4 Mwt-NSSS Power- [transmitted by pro-ject letter CQL-99-101].
- f. CN-SSO-99-8, Rev. 1, dated 9/21/99, "Harris Steamline Differential Pressure-High Technical Specification Setpoint for Uprate to 2912.4 blwt-NSSS Power" [transmitted by project letter CQL-99-100].
- g. CN-SSO-99-13, Rev. 1, dated 9/7/99, "Nuclear Instrumentation System Power Range Protection Functions for Harris tprate to 2912.4 Mwt-NSSS Power" [transmitted by project letter CQL-99-085).
CALCULATION NO. HNP-I/INST-1010 PAGE 4 REV. 0
- h. CN-SSO-99-14, Rev. 1, dated 12/17/99, "Harris (CQL) Nuclear Instru-mentation System Intermediate Range Protection Function for the Uprate to 2912.4 Mwt NSSS Power" (transmitted by project letter CQL-99-2292.
- i. CN-SSO-99-15, Rev. 1, dated 11/9/99, HRarris (CQL) Nuclear Instrumen-tation System Source Range Protection Function for the Uprate to 2912.4 Nwt NSSS Power" (transmitted by project letter CQL-99-176].
- j. CN-SSO-99-16, Rev. 1, dated 9/17/99, 'Containment Pressure Functions for Harris Uprate to 2912.4 Mwt-NSSS Power" [transmitted by project letter CQL-99-091].
- k. CN-SSO-99-17, Rev. 1, dated 1119/99, "Harris Reactor Coolant Pump Under Voltage/Under Frequency Setpoint Calculations for Uprate to 2912.4 Mwt - NSSS Power" [transmitted by project letter CQL-99-1751.
- 1. CN-SSO-99-18, Rev. 1, dated 10/20/99, 'Harris (CQL) Steam Flow /
Feedwater Flow Mismatch Function (Coincident with Steam Generator Water Level- Low) for Uprate to 2912.4 Mwt - NSSS Power" [trans-mitted by project letter CQL-99-146].
- m. CN-SSO-99-32, Rev. 0, dated 11/24/99, %Harris (CQL) Low, Low Tavg (P-
- 12) Technical Specification Setpoint for Uprate to 2912.4 Mwt - NSSS Power" [transmitted by project letter CQL-99-199].
- n. CN-SSO-99-33, Rev. 0, dated 11/30/99, "Harris (CQL) Low Reactor Coolant Flow Technical Specification Setpoint for Uprate to 2912.4 Hwt-NSSS Power" [transmitted by project letter CQL-99-203].
- 10. Westinghouse Project Letters (PUR/SGR design information sent to CP&L):
- a. CQL-98-028, dated 6/8/98, "Unverified Uncertainty Estimates".
- b. CQL-98-032, dated 7/6/98, 'Unverified Uncertainty Estimates Correc-tions".
- c. CQL-98-030, Rev. 1, dated 7/8/98, "Final PCWG Parameters for the SGR/ Uprating Analysis and Licensing Project".
- 4. CQL-99-013, dated 5/11/99, 'Revision to CQL Streaming Uncertain-ties'.
- e. CQL-99-029, dated 5/14/99, "Harris Not Leg Streaming Evaluation Sup-porting Docmentationl.
- 9. CQL-99-105, Rev. 1, dated 4/3/00, ýOTDT and OPDT Setpoints Operating Margins Evaluation for XNP Margin Recovery Program (WX705)".
- g. CQL-98-050, dated 11/3/98, "Revised RSC Level & Trip Setpoints in Consideration of Moisture Separator Modifications".
- h. CQL-98-052, dated 11/12/98, "Calculation Note - Harris RSG Recommend-ed SG Level Setpoints" [transmitted Calculation Note OPES (98)-025, dated 10/23/98, "SG NR Level Setpoints and PMA, Inputs For Shearon Harris Model A75 Replacement Steam Generators with Modified Moisture Separator Designm].
- 11. Westinghouse Technical and Nuclear Safety Notifications:
- a. Westinghouse Technical Bulletin ESBU-TB-97-02, dated 5/1/97, 'Analog Process Rack Operability Determination Criteriam.
- b. Westinghouse Technical Bulletin ESBU-TB-97-03, dated 5/1/97, tW Non-Conservative Aspect of the Generic Westinghouse Instrument Uncertain-ty Algorithm".
- c. Westinghouse Nuclear Safety Advisory Letter NSAL-97-01, dated 6/30/97, 'Transmitter Drift"o.
CALCULILTION NO. MNP-II/NST-1010 PAGE 5 REV. 3
- d. Westinghouse Nuclear Safety Advisory Letter NSAL-03-9, dated 9/22/03, "Steam Generator Water Level Uncertainties".
- 0. Westinghouse Technical Bulletin TB-04-12, dated 6/23/04, 'Steam Generator Level Process Pressure Evaluation".
- f. Westinghouse Nuclear Safety Advisory Letter, NSAL-02-3, Rev. 1, 4/08/02, *Steam Generator Mid-dock Plate Pressure Loss Issue".
- g. Westinghouse Nuclear Safety Advisory Letter NSAL-02-4, Rev. 0, 2/19/02, 'Maximum Reliable Indicated Steam Generator Water Level".
- h. Westinghouse Nuclear Safety Advisory Letter, NSAL-02-5, Rev. 1, 4/22/02, 'Steam Generator Level Control System Uncertainty issue".
- 12. CP&L Project Letters (design input information provided to Westinghouse):
- a. NW/98-013, dated B/4/98, '
Reference:
Letter 97-CQL-901t Request for Input Information for Setpoint/Uncertainty Analysis".
- b. nW/99-038, dated 4/1/99, "Design Inputs for WA Task 6 Protection System Setpoint Methodology for Uprated Power Conditions".
C. NW/99-033, dated 3/22/99, 'Design Inputs for WA Task 5 Pressurizer Water Level Control System Uncertainty Calculations for Uprated Power Conditions".
- d. HW/99-032, dated 3/22/99, 'Design Inputs for WA Task 4 Control Systems Uncertainty Calculations for Uprated Power Conditions".
- e. HW/99-097, dated 6/21/99, 'Design Inputs for RCP Undervoltage &
Underfrequency Protection System Trip Setpoints for Uprated Power Conditions (WA Task 6)".
- f. NW/99-116, dated 7/14/99, 'Response/Clarification to Open Issues in Letter CQL-99-035".
- g. HW/99-136, dated 8/12/99, 'Additional Design Inputs for XTDP Calorimetric Uncertainty Calculations".
X. nw/99-199, dated 10/12/99, "Clarification of Final Design inputs and Owner's Review C Uents for ITDP Calorimetric Uncertainty Calculations"o
- i. EW/99-021, dated 2/19/99, 'Calibration Procedures for WCAP 12340 (ITDP) Instrument Channels".
- j. HW/98-032, dated 12/28/98, "Design Input for RCS Streaming Evaluation . . . Task #2".
- k. HW/99-030, dated 3/10/99, 'Harris Cycle 8 Quadrant Power Tilt Ratio Design Input Data for the RCS Streoxming Report . . . Task #2".
- 1. NW199-009, dated 2/3/99, 'Design Inputs for Overtemperature and Overpower reactor Trip Setpoints".
X. HW/99-019, dated 2/18/99, 'Design Input, Analysis Value Trip Coefficients for the OPAT/OTAT Setpoint Evaluation". A. NW/99-147, dated 8/25/99, 'wwP SGR/PUR CP&L Approval of Final OPAT/OTAT Setpoints and Tau's".
- 0. HW/99-144, dated 7/14/99, "Additional Design Input Information for NIS Source Range (SR) and Intermediate Range (IR) Protection Trip Uncertainty Calculations".
- p. NW/99-034, dated 3/26/99, %Design Input, RCS Streaming Uncertainties for the W Design Verified Setpoint Uncertainty Calculation".
- q. HW/99-151, dated 9/3/99, 'Review Coze=nts for Uncertainty Calcula-tion associated with WBS Activity WX939 and WX971.
- r. HW/99-123, dated 7/16/99, "Pressurizer Pressure Control Uncertainty Calculation Inputs/Clarifications".
- s. TW/99-162, dated 9/10/99, 'Review Co=ents for Uncertainty Calcula-tion associated with WBS Activity WX987 and WX9790.
- t. NW/99-202, dated 10/14/99, "Owner's Review Co, ents for Steam Flow/Feedwater Flow Mismatch Uncertainty Calculation-.
- u. HW/99-248, dated 12/9/99, 'Owner's Review Corments for NIS Intermediate Range Protection Function Uncertainty Calculation".
CALCULATION NO. HNP-I/INST-1010 PAGE 6 REV. 3
- 13. Other CP&L-Generated PUR/SGR Design Input Documents:
- a. Uprate Fuel Analysis Plant Parameters Document [tUFAPPD], Rev. 3
[contained within Nuclear Fuels Section Calculation ENP-F/NFSA-0034, Rev. 3, "MM SGR/PUR Fuel Related Design Input Calculations"].
- b. HB/98-037, dated 6/2/98, "Letter DH/98-015 dated February 27, 1998, Design Input Required From CP&L-.
- 14. Plant Configuration Drawings:
- a. EHDRAC 1364-001328 S01 through S42, Westinghouse Process Control Block Diagrams [Westinghouse Drawing 108D803 Sheets I through 423.
- b. !VDRAC 1364-000064 through 1364-000878, Westinghouse Functional Diagrams [Westinghouse Drawing 108D831 Sheets I through 15].
- c. Drawing 2166-S-0302 Sheets 02, 07, & 08, Medium Voltage Relay Settings 6900 V Auxiliary Dun IA, 1B, & IC.
- 6. Drawing 2166-S-0302 Sheets 20, 23, & 24, Medium Voltage Relay Settings 6900 V Auxiliary Emergency Bus IA-SA & I1-SB.
- o. MDORAC 1364-002795 B01 and ZXDRAC 1364-003319, ETurbine Trip Low Fluid Oil Pressure Schematic and Wiring Diagram)
- f. Drawing 2165-S-0553 S03 and EMDRAC 1364-002724 [Turbine Throttle Valve Closure Turbine Trip Schematic and Wiring Diagram]
- 15. Plant Design Change Documents:
*. DC # 59631, "Instrument Uncertainty Evaluation for Steam Generator Level Trip Setpoints", Rev. 0. (Source Document for Steam Generator Process Measurement Accuracy Terms PMAy*,gro, PMAwaajt.&Dp, and 3.0 BODY OF CALCULXTION 3.1 Current Engineering/Licensing Basis Methodology As stated in Section 1.3 above, the original engineering methodology and operability determination bases, for values defined in the Tech Spec RTS/ESFAS Trip Setpoint Tables, were contained in Westinghouse Letter Report FCQL-355
[Reference 2.3]. This 'five-column" Tech Spec formatted methodology defines the following terms and their corresponding definitions.
" Trip Setpoint [TS]s Considered a nominal Reactor Trip value setting.
- Allowable Value [AV]s Accommodates instrument drift assumed between operational tests and the accuracy to which Trip Setpoint can be measured and calibrated. Defined using a "trigger value" ['T.O' per Letter Report FCQL-355.
* 'TA" or Total Allowances Difference (in percent of span) between Trip Setpoint and Safety Analy-sis Limit [SAL] assumed for Reactor Trip function; e.g., TA- ITS-BALI.
Defined within Tech Spec Equation 2.2-1 [ Z + R + S < TA 31 where 'R' includes Rack Drift and Calibration Uncertainties.
" %Z' Term:
Statistical sumation of analysis errors excluding Sensor and Rack Drift and Calibration Uncertainties.
" %'C (Sensor Error) Term:
Sensor Drift and Calibration Uncertainties. The last three terms were intended to further quantify channel operability
- mmV (when an As-Found calibration is outside its [rack] Allowable Value tolerance or Sensor Error 'S' allowance), by demonstrating that sufficient margin exists from the safety analysis limit.
CALCULATION NO. HUP-I/INST-1010 PAGE 7 REV. 0 Figure I herein was adapted from Figure 4-2 of Letter Report FCQL-355, to con-ceptually illustrate typical channel uncertainties in relation to the Safety Analysis Limit, Allowable Value, and Trip Setpoint. Figure 2 herein depicts the implementation for an instrument channel nominal setpoint, with respect to its (two-sided) rack calibration tolerance, its administratively controlled Tech Spec allowable value, and its normal operating range [or 'margin to trip']. Furthermore, Figure 2 shows the setpoint's relationship between its corresponding (FSAR Chapter IS) analytical limit and overall plant design safety 2lmit. Note that, an As-Found rack condition which exceeds a '% R' tolerance will re-quire readjustment to an acceptable As-Left condition [i.e., at nominal trip setpoint ITS' plus or minus 'R" tolerance]. (Similarly, sensor surveillance will confirm that the sensor is within an error tolerance defined by 'S'.) Table 1-1 herein provides a sunmmary of general equations/relationships per FCQL-355, used for computing each of the original "five-column" Tech Spec formatted terms. To demonstrate similarity with this original methodology, Table 1-2 herein provides a further sumary of equations/relationships used for the updated 'five-column" Tech Spec formatted term computations, given the [applicable PUR/SGR project-generated] uncertainty components. (For clarity of presentation, updated 'five-column" Tech Spec terms will be denoted herein as primed IX'3 terms.) As seen in Table 1-2, the need to 'minimize' sensor and rack uncertainties for operability purposes has been accomplished through the final definition used for the S' and AV' Tech Spec terms (i.e., consideration of only calibration and drift terms [as identified by (SD + SCA) and {RD + RCA), for sensor and rack, respectively])l this assures that a con-servatively small tolerance is used to administratively control/evaluate the As-Found/As-Left sensor and rack measurements, consistent with the FCQL-355 approach used for selection of the smallest of multiple trigger values and for operability determinations. Note that the 'Allowable Value' term contained in an updated Westinghouse
'ftwo-column" Tech Spec format (i.e., per methodology in WCAP-15249 and sup-porting Westinghouse calculation notes [References 2.8 and 2.9, respectively])
is not synonymous with the above 'five-column" 'Allowable Value' definition. In addition to the above-noted Tech Spec terminology, total loop uncertainty [TLUI, which is usually defined within Westinghouse uncertainty calculations as the channel statistical allowance [CSA], employs a calculational method that combines uncertainty components by elther: a square root of the sum of the squares (SRSS) technique for statistically and functionally independent [random) uncertainty errors; or by a conservatively treated arithmetic summa-tion technique of dependent uncertainties, and subsequent combination by SRSS with independent terms. These approaches are compliant with industry practices and CP&L guidance specified by References 2.6 and 2.7, respectively. Therefore, each instrument channel is evaluated for its applicable instrument uncertainty (including process measurement effects, M&TE/calibration accuracy, reference accuracy, pressure effects, temperature effects, drift, and other biases [where applicable]) for the sensor and rack electronics. Note that these uncertainties are similar to those shown in Figures I and 2 herein. 3.2 Inputs and Assumptions CP&L design inputs to Westinghouse uncertainty calculations [Reference 2.9 listing] included conservative CP&L determination of various uncertainty effects for sensors and rack electronics [e.g., reference accuracy, calibration accuracy, measurement & test effects, applicable sensor pressure
CALCULATION NO. RNP-I/INST-1010 PAGE 8 REV. 0 and temperature effects, electronics temperature effects, drift, etc.]. These determinations were provided as CP&L design inputs by Reference 2.12 project correspondence. The following inputs and assumptions are specifically noteworthy, and have been applied within computations summarized herein (unless noted otherwise):
- 1. Continued use of "five-column" formatted terms and their corresponding definitions (per current Tech Spec surveillance requirements and bases) remain applicable. Since References 2.8 and 2.9 were prepared to the Westinghouse vtwo-column' methodology, 'Allowable Value' terms specified in References 2.8 and 2.9 do not apply, and should be ignored (to avoid confusion with conclusions herein). [However, for ease of reference, Table 2-1 herein consists an excerpt of WCAP-15249, Table 3-21.1
- 2. CP&L and/or Westinghouse-generated design inputs [per References 2.13 and 2.10 listings, respectively] define PUR/SGR-related nominal trip setpoints and associated analytical limits for specific RTS/ESFAS func-tions. As noted in Tables 3-1 through 3-29, some protection functions do not have identified safety analysis limits (within existing Chapter 15 safety analyses); these channels are used for diversity, but the analysis do not explicitly model or take credit for their actuation.
- 3. Unless specifically designated to be a dependent uncertainty component, process measurement uncertainty effects (designated as PMA or PEA) are generally considered to be independent (or random) of both sensor and rack uncertainty parameters. Examples of PMA components include effects due to neutron flux, calorimetric power neasurement uncertainty assumptions, fluid density changes, reference leg heatup, effects of head correction, and temperature stratification/streaming assumptions.
Examples of PEA components include uncertainties due to metering devices (such as flow elbows and venturis). When the condition monitored has a trip on an increasing process condition, only the negative uncertainties are considered for the calculation. When the condition being monitored has a trip on a decreasing process condition, only the positive uncertainties are considered for the calculation. The calculation below groups both the positive and negative uncertainties together in a conservative manner, that may be applied in either direction.
- 4. Calibration (i.e., SCA and RCA) and Drift (i.e., SD and RD) uncertain-ties are defined as rando with normal distributions [see Reference 2.8, Sections 2.2 and 2.31. Calibrations are performed under [MST/LPJ proce-dural control with two-sided calibration tolerances. Sensors will drift either high or low from the as-left values. For these reasons, the un-certainties are expected to be random with normal distributions.
- 5. Uncertainty components are defined using a 95% probability and high con-fidence level, consistent with the original Westinghouse FCQL-355 methodology [Reference 2.31 and PUR/SGR-generated documents (per Refer-ences 2.8 and 2.93.
- 6. Published sensor manufacturers' performance specifications generally show drift over a specific time duration. Where such specifications are cited, an 18-month + 25% [or 22.5-month) minimum MST/LP calibration frequency has been used within Westinghouse uncertainty calculations
[per References 2.8 and 2.91.
- 7. Sensor drift component was chosen as "bounding' [worst-case maximum]
values (based upon As-Found and previous As-Left MST/LP calibration data comparisons), which was considered to be conservative for the computation purpose4 of each CSA term; these SD values have been re-tained within the computation of applicable "five-column* Tech Spec
CALCULATION NO. HNP-IXINST-1010 PAGE 9 REV. 0 terms. [See Reference 2.8, Section 2.1 for additional discussion.] Where a turndown factor exists for a specific sensor function, each SD value will be multiplied by its corresponding turndown factor, unless justified otherwise (within its Tables 3-1 through 3-29 details).
- 8. Three-up/three-down calibrations are not performed for transmitters within MST/LP procedures. Therefore, CSA results are computed using the sensor reference accuracy (SRA) term. SRA Values are generally obtained from manufacturer's published product specifications. Although proce-dure revisions are unlikely, if calibration techniques included multiple passes over the entire instrument range (to verify conformity, hyster-esis, and repeatability effects), then the SRA term could be eliminated from the CSA uncertainty computation.
- 9. Based upon MST/LP calibration methods, credit is taken in the uncertain-ty calculation for the loop-calibration of process channels (with a test signal at the input of the process instrument channel and a complete loop calibration to the final device). Therefore, only one RCA term is used for the total rack calibration tolerancel a rack comparator set-ting accuracy [RCSA], as originally specified in Reference 2.3, is not used in the CSA (or in Tech Spec Allowable Value term).
- 10. Teise (or equivalent) pressure gauges used for transmitter calibrations are temperature compensated to 95*Fp calibrations performed in ambients above 959F will compensate for the specific increased ambient. The DVM (of a type as required by the )IST/LP) is used generally within the temperature range of 15*C to 35*C [597F to 957J1, as identified In the DMV specification.
- 11. Sensor and rack )&TE [SMTE and RMTE] uncertainties have been specified as statistically dependent upon drift and calibration uncertainties in (Reference 2.9) Westinghouse calculation notes, which assures that the CSA determination is more conservative (than without such consideration of interactive parameters).
- 12. Sensor pressure effects ISPE] and sensor temperature effects [STE],
where applicable, are generally based upon manufacturer's published product specifications. (SPE compionents are typically applicable only to differential pressure transmitters.) CTZ values will incorporate applicable turndown factors, unless justified otherwise.
- 23. Rack temperature effects [RTE] are based upon historical Westinghouse performance data, and can be considered to reflect uncertainty values at a 95% probability and 95% confidence level. In general, an RTE term of 0.5% of span was used in the CSA/Tech Spec uncertainty calculations, based upon Reference 2.3.
- 14. Rack drift [RD] was generally assumed as a (worst-case) conservative value of 1.0%of span for the purpose of CSA uncertainty calculations.
- 15. Environmental allowance [EA] uncertainty components are generally limited to RTS/ESFAS trip functions which must be postulated to occur at a delayed post-accident (LOCA/MSLB] time duration. Sensors installed in containment or steam tunnel locations may require an EA component. A basis for EA uncertainty component values has been included in the applicable Table 3-x reference.
- 16. Seismic effects are not assumed, owing to the fact that (previously performed) seismic qualification testing has demonstrated successful response/acceptance criterion. Furthermore, after a seismic event, the plant is shutdown and instruments would be recalibrated (to required performance specifications/tolerances).
CALCULATION NO. HNP-IZ/NST-1010 PAGE 10 REV. 1 in addition, seismic effects on OTAT/OPAT channels have been further evaluated (as noted in Reference 2.12.1 [HW/99-0093). A seismic allow-ance is not required for the OTAT reactor trip, since the MNP design basis requirements do not postulate a seismic event simultaneously with a non-LOCK transient that may require the OTAT trip. The OTAT trip is not required for LOCA events. Xn the event of a seismic disturbance, the pressure transmitter calibration would be suspect and require evaluation and possible recalibration.
- 17. This calculation will address, in particular, those changes to trip setpoints and/or analytical limits that have been changed specifically for PUR/SGR-related analyses and/or system configurations. Tables 2-2 and 2-3 provide a summary of such changes to trip setpoints and analytical limits, for RTS and ESFAS functions, respectively. These changes are a result of the following:
0 For SG N-R Level trip functions, the [Model A75] replacement steam generators IRSGs] have a different physical design configuration (e.g., larger tap-to-tap dimension, different top of U-tube bundle, elimination of pro-heat feedwater design, etc.), which results in the need for different normal operating control water level and for RTS/ ESFAS trip setpoints (for Low-Low, Low, and High-High trip functions, as defined per References 2.10.g and 2.10.h.]. PURISGR analyses have utilized updated safety analysis limits [as originally defined in References 2.10.a, 2.10.b, & 2.13.a and subsequently reconciled per Reference 2.9]. Revised Tech Spec term values correspond to these new RSG setpoint requirements, as noted in Tables 3-10A through 3-10C and Table 3-18 herein.
- For OTAT/OPAT trip functions, Reference 2.10.f provides the justifi-cation for: elimination of TI/T 2 lead/lag compensation and addition of T3 lag filter (for each RCS loop's measured AT): and changes to other trip function coefficients/time constants. PUR/SGR implementa-tion will be based upon updated safety analysis limits (compatible with function values defined in Reference 2.10.f3. Tech Spec values must be revised accordingly, as shown in Tables 3-5 and 3-6 herein.
- Containment Pressure High-I and High-2 setpoints have slightly increased safety analysis values (as compared to Reference 2.3).
Refer to Table 3-12A herein for Tech Spec term changes.
- A Pressurizer Level High setpoint uncertainty lof 6.75% level span]
has been [recently] defined within PUR/SGR safety analyses: this un-certainty was applied against a 100% filled pressurizer level condi-tion. (Reference 2.3 did not previously specify a safety analysis limit.) As such, the current Tech Spec trip setpoint continues to apply, in relation to a 100% level analytical limit, as noted per Table 3-8 herein.
- 18. In lieu of simplified loop diagrams, refer to existing MnP process control block diagrams, functional diagrams, and/or other plant configuration drawings [as noted per Reference 2.14 listing above].
3.3 Calculation Synopsis This document delineates the channel statistical allowance (CSA) and the "five-column" Tech Spec terms for each RTS/ESFAS Trip Setpoint function. Tables 3-1 through 3-29 herein summarize these calculation results. (For ease of reference, Table 3-0 contains an index of these calculation summaries for each trip function [with its corresponding Tech Spec Table item No.].)
CALCULATION NO. ENP-I/INST-1010 PAGE 11 REV. 0 The CSA result combines applicable uncertainty components [described in Sec-tion 3.11 using a "square root of the sum of the squares" (SRSS) calculational technique. This technique has been used in both past and current Westinghouse methodologies (per References 2.3 and 2.8], as well as within current industry and CP&L guidance (per References 2.6 and 2.73. The "updated' Westinghouse uncertainty calculations and associated WCAP [References 2.8 and 2.93, which were produced for the PUR/SGR projects, combine uncertainty components in the following general equation formula (also *Eq. 2.1' of Reference 2.83: CSA r 2 (PMA)2 + (PEA)2+ (SHTE+SD)a+ (SPE) + (STE) + (SRA) 21 L + (SMTE SCA) 2 + (RMTE+RD)2+(RTE) 2
+ (RMTE+RCA) 2 J
+ EA + SEISMIC + BIAS where:
PMA. a Process Measurement Accuracy PEA 0 Primary Element Accuracy SRA W Sensor Reference Accuracy SCA a Sensor Calibration Accuracy SMTE a Sensor Measurement and Test Equipment (Accuracy) SPE a Sensor Pressure Effects STE Sensor Temperature Effects SD a Sensor Drift RCA 0 Rack Calibration Accuracy RMTE M Rack Measurement and Test Equipment (Accuracy) RTE a Rack Temperature Effects RD Rack Drift ZA Environmental Allowance (treated as a Bias] SEISMIC Seismic Allowance [treated as a Bias) BIAS Other Non-Random/Dependent Uncertainty Component(s) The CSA results from *updated' Westinghouso uncertainty calculations (produced for the PUR/SCR projects (per References 2.93), for each RTS/ESFAS trip function, have been suimmarized within Table 3-21 of WCAP-15249 [Reference 2.8]. In addition, Table 3-21 of WCAP-15249 has also been excerpted as Table 2-1 herein, for ease of reference to uncertainty terms and CSA results for each trip function. Based upon the relationships shown in Figures I and 2, portions of the overall CSA have been defined in terms of the Tech Spec terms (as specified above in Section 3.1, and within Tables 1-1 and 1-2). Any variations from the above generalized equation format and/or uncertainty components are defined in specific trip function summaries (within Tables 3-1 through 3-29). Although interrelated, the CSA uncertainty and the Tech Spec terms are generally evaluated in different ways, as noted by the following evaluation circumstancess 0 The CSA term is typically composed of conservatively-chosen (increased) values for uncertainty components, to maximize the overall channel uncer-tainty (for comparison of available margin between the nominal setpoint and safety analysis limit) relative to their 95% probability and high (or 95%, as applicable for power/flow calorimetric functions) confidence level.
CALCULATION NO. HNP-I/INST-1010 PAGE 12 REV. 0 Rowever, N the "five-columnn Tech Spec allowable value [AVI has been conser-vatively chosen (smaller) based upon the smallest trigger term [TN] as defined/required by Reference 2.3, to minimize the Tech Spec surveillance tolerance used for rack calibration/drift allowances. Sensor Error [S] is also correspondingly minimized using calibration/drift allowances only. In addition, deviations from current Tech Spec term values must be balanced in relation to: the level of conservatism provided by the current surveillance; the operational conditions/considerations associated with the RTS/ESFAS trip function; and the practicality of surveillance testing (e.g., ease of testing process, repeatability of test results, etc.). Where post-PURISOR implementa-tion Includes no hardware changes (independent of channel normalization/ scaling), evaluation of specific trip function summaries [per Tables 3-1 through 3-29] will detail those cases where deviations from current Tech Spec values are not warranted.
4.0 CONCLUSION
S Computation summaries of (post-PUR/SGR) instrument channel uncertainties and "five-column Tech Spec terms for each RTS/ESFAS function are presented [with a corresponding documentation source reference] in Tables 3-1 through 3-29 herein. The applicability and acceptability of these results are discussed per the following: 4.1 Channel Statistical Allowance (CSA) Results The acceptance criterion for the trip channel results requires that positive setpoint margin exists. This calculational margin is defined as the differ-once between the channel's total allowance [TA] and the channel statistical allowance [CSA). (As specified in Section 3.0, the total allowance is defined as the difference between safety analysis limit and the nominal trip setpoint [in percent of span].) References 2.8 and 2.9 results, as excerpted within Table 2-1 and as specified within Tables 3-1 through 3-29, demonstrate that all trip setvoints possess a specific positive calculational margin between its-TA and CSA result; there-fore, acceptability of each function's nominal trip sotpoint is demonstrated. Unless specifically excepted (and reconciled) herein, the CSA terms presented herein agree with values specified in PUR/SGR-related Westinghouse documenta-tion listed under References 2.8 and 2.9. These results supercede the origi-nal values provided within Reference 2.3 [FCQL-3551, and comply with updated calculational methodology (as described per Section 3.3). 4.2 Summary of "Five-Columnm Tech Spec Terms Tables 3-1 through 3-29 also detail applicable 'five-columnv Tech Spec terms ETA, Z, S, Trip Setpoint, and Allowable Value) for each trip function. These Tech Spec terms are based upon either: values evaluated to be the same as current Tech Spec terms; or values computed by general equations shown in Table 1-2. %ka.) Tables 4-1 and 4-2 include a mark-up of current Tech Spec Tables 2.2-1 and 3.3-4, respectively, to support the PUR/SGR licensing amendment; furthermore, for ease of comparison, PUR/SGR Tech Spec changes have also been highlighted within Table 4-3. These Tech Spec changes retain the original MNPengineering and licensing bases (as defined in Reference 2.3 [FCQL-355]), and demonstrate
CALCULATZON NO. UNP-Z/INST-1010 PAGE 13 REV. 0 continued (post-PUR/SCR) compliance to HNP Tech Spec RTS/ESFAS Trip Setpoint requirements. As such, use of these updated Tech Spec terms are suitable within corresponding scaling calculations, MSTs/LPs, and other documents that require update as a result of PURISOR project implementation. The "five-columnO Tech Spec terms presented herein will not agree with 'two-column" values/terminology specified in PUR/SGR-related Wet-inghouse documen-tation listed under References 2.8 and 2.9. Similar to CSA results (as noted in Section 4.1 above), the 'five-columnv Tech Spec terms presented herein supercede the original values provided in Reference 2.3; however, operability methodology of Reference 2.3, Section 4.0 remains applicable (owing to its compliance with the existing HNP licensing bases [as delineated in Tech Spec Bases B 2.2, B 3/4.3.1, and B 3/4.3.23).
CALCULATION NO. MNP-I/XNST-1010 PAGE 14 REV. 0 FIGURE 1 CHANNEL UNCERTAINTY COMPONENTS RELATIVE TO SAFETY ANALYSIS LIMIT, ALLOWABLE VALUE, AND TRIP SETPOINT Safety Analysis Limit (SAL) 1 Process Measurement Accuracy J 1 Primary Element Accuracy J 1 Sensor Temperature Effects J 1 Sensor Pressure Effects J 1 Sensor Calibration Accuracy J 1 Sensor Drift J 1 Environmental Allowance J 1 Rack Temperature Effects STS Allowable Value (AV) 1 Rack Calibration Accuracy J 1 Rack Drift J STS Trip Setpoint (TS) J
- - Includes Rack ComVarator Setting Accuracy (RCSA).
(Adapted from W Letter Report FCQL-355 (Rev. 1), Figure 4-2 [Page 4-11).)
CALCUrLTION NO. IMP-X/XNST-l1O1 PAGE is REV. 0 FIGURE 2 OPERATING CONDITIONS, UNCERTAINTIES, AND MARGINS RELATIVE TO SAFETY ANALYSIS LIMIT, ALLOWABLE VALUE, AND TRIP SETPOINT Failure Limit Safety Margin Acceptance Limit Design Margin Analytical Limit (Safety Analysis Limit [SAL]) Calculational Margin Total Allowance [TA] Channel Statistical Allowance [CSAJ (includes Z, S, & R Components) Allowable Value [AV] Bistable Trip Setpoint ITS] Rack Tolerances [+/- R] _ _ Normal Plant Operating Conditions (Operating Margin to Trip Setpoint) Note: Figure is intended to provide relative position and not to imply direction. (Adapted from ZSA S67.04-1994, Figure 1)
CALCU)LTION NO. HNP-IMINST-1010 PAGE 16 REV. 0 TABLE 1-1 SUM1ARY OF GENERAL EQUATIONS/RELATIONSHIPS USED IN REPORT FCQL-355 FORMAT General Notes: All terms are in Percent of Span, unless noted otherwise. 1*" designates one of the "five-column" Tech Spec terms. CSA Channel Statistical Allowance ((PMA)2 + (PEA) 2 + (SCA+SD) 2 + (STE) 2 + (SPE) 2 + (RCA+RCSA+RD) 2 + (RTE) 2) 1 /2 + EA S Sensor Error Term *
= SCA + SD A Sum of the squares of all Random Errors that are not associated with SCA, SD, RCA, RCSA, or RD 2 + (STE) 2 + (RTE) 2 (PMA) 2 + (PEA) 2 + (SPE)
SAL = Safety Analysis Limit (in engineering units) TS = Trip Setpoint (in engineering units)
- TA Total Allowance [where TA > Z + R + S3]
TS - SAL [for a Low Setpoint] OR SAL - TS [for a High Setpoint] T Rack Trigger Value TA - [(A + S 2 )212 + all Bias terms] OR (RCA +RCSA+RD) AV = Allowable Value (in engineering units) *
= TS - T [for a Low Setpoint] OR TS + T (for a High Setpoint]
Z Statistical summation of errors excluding those associated with SD, SCA, SMTE, RD, RCA, RCSA, and RMTE * (A)"1 2 + any Bias terms Margin TA - CSA
CALCULATION NO. )IP-VI/NST-l010 PAGE 17 REV. 0 TABLE 1-2
SUMMARY
OF GENERAL EQUATIONS/RELATIONSHIPS USED FOR THE UPDATED "FIVE-COLUMN" TECH SPEC FORMAT General Notes: All terms are in Percent of Span, unless noted otherwise.
' designates one of the -five-column" Tech Spec terms.
Primed terms (X') represent updated [PUR/SGR-related] terms. CSA" uncertainty components below reflect updated PUR/SGR values. Background/Development: CSA' channel Statistical Allowance C {(PMA) 2 + (PEA) 2 + (SMTE+SD)2 + (SPE) 2 + (STE) 2 + (SMTE +SCA) 2 + (SRA) 2 + (RMTE+RD) 2 + (RTE) 2 + (RMTE+ RCA) 2) 1 /2 + EA + Biases This equation can be rearranged per FCQL-355 terminology, by inspection: CSA' = ( A' + S'2 + R,2 )1/1 + EA' + Biases' 2 2 where: A' - (PMA) + (PEA)2 + (SPE) + (STE) 2 + (RTE) 2 2 1 S, . j[(SMTE + SD) 2 + (SM4TE + SCA) 2 + (SRA) ] /2 2 1 2 R" = [(RMTE + RD) 2
+ (RMTE + RCA) ]3 Z" = (A') 1 / 2 + EA + Biases However, to conservatively maintain minimum tolerances on S" and R' terms, define S' and R' (as originally specified in FCQL-355) in terms of updated PUR/SGR components (where RCA includes bistable accuracy [i.e., original FCQL-355 RCSA term]):
S' = SD + SCA R I- RD + RCA Since FCQL-355 relationship {TA' > Z' + R' + S') must remain valid, alternately confirm the acceptabilit7y for R', by solving the TA' inequality relationship for a minimum R' [once S', Z', and TA' are known]. R' = { TA' - Z' - S' ) Note that the above "check" yields an equal (or smaller) value for R' than use of the FCQL-355 T2 1 - ( TA" - [(A' + (S,)2)212 + all Biases) ) expression.
CALCULATION NO. HNP-I/INST-1010 PAGE 18 REV. 0 TABLE 1-2 (Cont'd)
SUMMARY
OF GENERAL EQUATIONS/RELATIONSHIPS USED FOR THE UPDATED "FIVE-COLUMN1 TECH SPEC FORMAT Computational Methodology: All Tech Spec terms can be determined in the following manner, given known values [denoted below by %**']. (Provide reference for %**" known values.) CSA' = Per equation (above) containing all upgraded PUR/SGR uncertainties SAL' = Safety Analysis Limit (in engineering units)
- Margin' TA' - CSA' TS' - Trip Setpoint (in engineering units) *,**
TA' = Total Allowance * = TS' - SAL' [for a Low Setpoint] OR SAL' - TS' [for a High Setpoint] S" SD + SCA [as noted above]
- A' (PMA) 2 + (PEA) 2
+ (SPE) 2 + (STE) 2 + (RTE) 2 [as noted above]
1 Z" (A') /2 + EA + Biases (as noted above]
- T = Rack Trigger Value
= lesser oft R' = [RD + RCA] OR [TA' - Z' - (SD + SCA)]
AV' = Allowable Value (in engineering units) *
= TS' - T' [for a Low Setpoint] OR TS' + T' [for a High Setpoint)
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CALCULXTION NO. RNP-XIXNST-1010 PAGE 20 REV. 0 TABLE 2-2 PUR/SGR-RELATED CHANGES TO RTS SETPOINTS AND ANALYTICAL LIMITS TS Table 2.2-1 Item I Trip Parameter TS Trip Setpoint Safety Analysis Limit 2.a /
- 109% of RTP 118% of RTP (1)
Power Range High Setting 2.b /
- 25% of RTP 35% of RTP (1)
Power Range Low Setting 3/
- 5% of RTP with a time N/A (5)
PR High Positive Flux Rate constant of > 2 sec (5) a / < 5% of RTP with a time -8.00% of RTP With a PR High Negative Flux Rate constant of > 2 see > 2 sec time constant (2) 19.c I < 49% of RTP 58% of RTP (1) Neutron ?lux P-9 Interlock (for Single Loop Loss of Flow Trip Block) 5/ < 25% of RTP (5) N/A (5) Intermediate Range High 6/ .< 105 cps (5) N/A (5) Source Range High 7&8 1 Dolta-T setpointx, per 1 Delta-T allowable values, Overtecverature and Overpower function as defined by !per function as defined by Delta-T Tech Spec revision (1) Tech Spec revision (1) 9 / 20.1960 pnia (.) 1920 psig (1) Low PZR Pressure Trip 10 / < 2385 psig (1) 2445 psig (1) High PZR Pressure Trip 11 / < 92% of span (5) H/A (5) Pressurizer Water Level - 100% (max. value) assumed High Ffor uncertainty calcula-I tion; SPC Safety Analysis assumes a 6.75% control channel uncertainty. c 12 / Low Primary Coolant Flow
- 90.5% of loop full indicated flow (1) k85%
flow of loop full Indicated (2) 13 / > 25% of N-R span ,See (3) below. Low-Low S0 Level Trip S(3),(41)
CALCULATION NO. HNP-I/INST-1010 PAGE 21 REV. 0 TABLE 2-2 (Cont'd) TS Table 2.2-1 Item / Trip Parameter TS Trip Setpoint Safety Analysis Limit 14 / : 25% of N-R span See (3) below. B Low SO Level (coincident (3),(4) with Steam/Feedwater Flow Mismatch) I. 14 / < 40% of full steam flow Nil. ( 5) Steam/Feedwater Flow at RTP (5) Mismatch (coincident with Low So Level) Table 2-2 Notes: (1) - As noted In Reference 2.10.& [CQL-98-028] and/or Reference 2.10.b [CQL-98-032). Reference 2.13.a [UFAPPD] confirms this value for SPC Safety Analysis. (2) - As revised by Reference 2.10.a [CQL-98-028) and/or Reference 2.10.b [CQL-98-032]. Reference 2.13.a [UTAPPD] confirms this value for SPC Safety Analysis. (3) - 5/5/98 & 516/98 meeting minutes attached to CQL-98-028 recornended the following analysis values:
- a. For outside containment steam line breaks, accident cases should use a 0% of span SAL for the S0 Low-Low Level Trip.
- b. For loss of normal feedwater and for auxiliary feedwater Initiation, a 16.1% of span SAL (corresponding to the top of the RSO tubes) should be used.
C. For feedawter 2ine break~s, a 0% of span VAL should be used. Reference 2.13.a [UFAPPD] confirms this value for SPC Safety Analysis. (4) - Specified within CQL-98-050. (Note that High-High SO Level setpoint and SAL Ifor a foedwater system malfunction) were originally specified as 79% and 100%, respective-ly, In CQL-98-032; the 'final* 78% of span setpoint value was selected based upon the evaluation documented per CQL-98-050.) Reference 2.13.& [UFAPPD1 confirms this value for SPC Safety Analysis. (5) - Not used in SPC Safety Analysis. Current TS trip setpoint value shown.
CALCUrATION NO. HNP-I/INST-1010 PAGE 22 REV. 0 TABLE 2-3 PUR/SGR-RELATED CHANGES TO ESFAS SETPOINTS AND ANALYTICAL LIMITS TS Table 3.3-4 Item I Trip Parameter TS Trip Setpoint Safety Analysis Limit l.c / < 3.0 psig (1) 5.0 psig (1) Containment Pressure High-1 . SAL subsoeqntly Increased Safety Injection *in SPC Safety Analysis and in iWI containnt analy-smis 3.a(3) and 3.a(3) / 3.0 psig (6) 5.0 psig (6) Containment Pressure Righ-1 : SAL increased (as noted for Phase A Cont. esol. and abaoe) Cont. Ventilation Isol. 4.c / 3.0 psig (5) N/A (5) Containment Pressure ligh-2 MS Line Isolation 2.c / < 10.0 psig (1) 12.0 psig (1) Containrmnt Pressure fligh-3 Containment Spray 3.b(3) / 10.0 puig (6) 12.0 psig (6) Containment Pressure High-3 Phase D Containment Xsol. 1.d / > 1850 psig (1) 1699.6 psig (1) Low PZR Pressure - 81 Trip 5.b and 10.d / C 78% of N-R sparn (4) 100% of N-R span (4) High-High SO Level for Turbine Trip & rW Isolation IP-141 6.c / > 25% of N-R span (3) See (3) below. Low-Low SO Level for Auxiliary Feedwater initiation 10.b I > 553 Or (5) N/A (5) Low-Low Tavg, P-12 ZSr Interlock 1.. /
- 601 psig (1) 370.9 psig (1), (7)
Steamline Pressure - Low (Safety Injection) 4.d / *601 psig (11) 370.9 psig (1), (7) Steamline Pressure - Low (MS Line Isolation)
CALCULATION NO. HNP-1/INST-1010 PAGE 23 REV. 0 TABLE 2-3 (Cont'd) TS Table 3.3-4 Item I Trip Parameter TS Trip Setpoint Safety Analysis Limit 4.e / < 100 psi (5) N/A (5) Negative Steamline Rate - Nigh (for MS Line Ieal.) 6.g / < 100 psi (1) 165 psi (1) Steamline Differential Pressure - High, coincident with MS Line Isolation (Aux rW Isolation) Table 2-3 Notes: (1) - As noted in Reference 2.10.a ICQL-98-028] and/or Reference 2.10.b [CQL-98-032]. Reference 2.13.& [UFAPPD] confirms this value for SPC Safety Analysis. (2) - As revised by Reference 2.10.a [CQL-98-0281 and/or Reference 2.10.b (CQL-98-032]. Reference 2.13.a [UFAPPD] confirms this value for SPC Safety Analysis. (3) - 5/5/98 & 516/98 meeting minutes attached to CQL-98-028 recommended the following analysis values:
- a. For outside containment steam line breaks, accident cases should use a 0% of span SAL for the SO Low-Low Level Trip.
- b. For loss of normal feedwater and for auxiliary feedwater initiation, a 16.1% of span SAL (corresponding to the top of the RSO tubes) should be used.
- d. For feedwater line breaks, a 0% of span SAL should be used.
Reference 2.13.a EUFAPPD) confirms this value for SPC Safety Analysis. (4) - Specifiad within CQL-98-050. (Note that High-High SO Level sotpoint and SAL [for a feedwater system malfunction] were originally specified as 79% and 100%, respective-ly, In CQL-98-032; the %final' 78% of span setpoint value was selected based upon the evaluation documented per COL-98-050.) Reference 2.13.a IUFAPPD3 confirms this value for SPC Safety Analysis. (5) - Not used In SPC Safety Analysis. Current TS trip setpoint value shown. (6) - Per current TS Table, same value as Item I.c (for High-i) or Item 2.c (for High-3). (7) - Westinghouse PUR analysis used an analytical value of 542.2 psig, which excludes MSLD-related environmental allowances (MA) uncertainties.
CALCULATION NO. HNP- -IIINST-1010 PAGE 24 REV. 0 TABLE 3-0
SUMMARY
OF CSA AND FIVE-COLUMN TECH SPEC TERMS INDEX OF CALCULATION
SUMMARY
TABLES TS TABLE WCAP- INST- W CALC OR 2.2-1 15249 1010 OTHZR Ma TABLE CALC REF(s) rN~CTIOI _ESCRIPTZON ITEMLS) 3-ABL Power Range, Neutron Flux-Nigh Setpoint 2.a 3-1 3-1A CN-SSO-99-13 Power Range, Neutron Flux-Low Setpoint 2.b 3-1 3-lB CN-SSO-99-13 Power Range, Neutron Flux-High Positive Rate 3 3-2 3-2B CN-SSO-99-13 Power Range, Neutron Flux-Nigh Negative Rate 3-2 3-2A CN-SSO-99-13 Intermediate Range, Neutron Flux 3-3 3-3 CN-SSO-99-14 Source Pang*, Neutron Flux 3-4 3-4 CN-SSO-99-15 Overte*perature AT 7 3-5 3-5 CN-TSS-98-33 Overpower AT 8 3-6 3-6 CN-TSS-98-33 Pressurizer Pressure - Low, Reactor Trip 9 3-7 3--7A CN-SSO-99-03
- ,, Pressurizer Pressure - High, Reactor Trip 10 3-7 3-7D CN-SSO-99-03 Pressurizer Water Level - High 11 3-8 3-8 CN-SSO-99-5 Reactor Coolant Flow - Low 12 3-9 3-9 CN-SSO-99-33 So Water Level, Low-Low (7W Line Break) 13 3-10a 3-10A CN-TSS-98-19 SO Water Level, Low-Low (Loss of Normal rW) 13 3-10b 3-10D CH-TSS-98-19 Steam Generator Water Level, Low 14 3-10c 3-10C CN-TSS-98-19 Steam / Feedwater Flow Mismatch 14 3-11 3-11 CN-SSO-99-18 Reactor Coolant Puno Undervo*tage - Low 15 3-19 3-19 CN-SSO-99-171 E2-0010 Reactor Coolant Pum Underfrequency - Low 16 3-20 3-20 CN-SSO-99-17; Z2-0011 Low Fluid Oil Pressure, Turbine Trip 17.a N/A 3-21 INST-1055 Turbine Throttle Valve Closure, Turbine Trip 17.b N/A 3-22 INST-1054 P-6, Intermediate Range Neutron Flux 19.a N/A 3-26 CN-SSO-99-14 P-7, Low Power Rx Trip Block (from P-10 input) 19.b(1) N/A 3-27 CN-SSO-99-13 P-7, Low Power Rx Trip block (from P-13 Input) 19.b(2) N/A 3-27 N/A P-8, Power Range Neutron Flux 19.c N/A 3-28 CN-SSO-99-13 P-10, Power Range Neutron Flux 19.d N/A 3-27 CN-SSO-99-13 P-13, Turbine Impulse Chamber Pressure 19.e N/A 3-27 N/A
CALCUL&TION NO. o MP--I/INST-1010 PAGE 25 REV. 1 TABLE 3-0 (Cont'd)
SUMMARY
OF CSA AND FIVE-COLUMN TECH SPEC TERMS INDEX OF CALCULATION
SUMMARY
TABLES TS TA3LE WCAP- ZKST- W CALC OR 3.3-4 15249 1010 OTHER mNP 1,NCT ON DESCR1IPTIZO TABLE CALC PEF 8) Containment Pressure - High-i l.c 3-12 3-12A CN-SSO-99-16 Containment Pressure - High-2 4.c 3-12 3-12A CN-SSO-99-16 Containment Pressure - High-3 2.c 3-12 3-12D CN-SSO-99-16 Pressurizer Pressure - Low, Safety Injection 1.d 3-13 3-13 CN-SSO-99-03 Steamline Differential Pressure -High 6.g 3-14 3-14 CN-SSO-99-8 Negative Steamline Pressure Rate - High 4.e 3-15 3-15 CN-SSO-99-7 Steamline Pressure - Low 1.e 3-17 3-17 CN-SSO-99-7 90 Water Level - High-High, Barton 764 Xmtrs 5.b 3-18a 3-18 CN-TSS-98-19 S0 Water Level, Low-Low 6.c 3-10a 3-10A CN-TSS-98-19 RWST Level - Low-Low 7.b NIA 3-23 INST-1030
- 6.9 KV E-Bus Undervoltage - Primary, LOOP 9.a N/A 3-24 0054-JRG 6.9 KV Z-Bus Undervoltage - Secondary, LOOP 9.b K/A 3-25 Z2-0005.09 P-Il, Pressurizer Pressure 10.a N/A 3-29 CN-SSO-99-03 NOT P-11, Pressurizer Pressure 10.a NIA 3-29 CN-SSO-99-03 P-12, Low-Low Tavq 10.b 3-16 3-16 CN-SSO-99-32
CALCULATION NO. RHNP-IIINST-1010 PAGE 26 REV. 0 TABLE 3-1A POWER RANGE, NEUTRON FLUX - HIGH SETPOINT Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA' a [ (PMl) 2
+ (PMAI2 ) 2 + (PEA) 2 + (SHTE + SD)2 + (STE) 2 + (SPE)2 +
2 2 2 (SCA + SMTE) 2 + (SRA) ]112 2
+ (RMTE + RD) + (RTE) + (RCA + RMTE)
S- [ (1.67)2 + (4.17)2 + (0.00)2 + (0.00 + 0.00)2 + (0.00)3 + (0.00)2 + (0.00 + 0.00)2 , (0.00)2 + (0.05 + 1.00)2 + (0.83)2 + (0.50 + 0.05)2 ]112 4.72 % Span [Reference 2.9.g & Reference 2.8 (WCAP Table 3-1)] Note that all sensor uncertainties are set to zero, owing to channel normalization based upon daily power calorimetric surveillance [and adjustment (as required)] or based upon STE accounted for through PHA neutron flux effects uncertainty. TS - 109.0 % RTP IReference 2.13.a LUFAPPD, Table 2.2)] SAL - 118.0 % RTP [Reference 2.13.a (UFAPPD, Table 2.2)) k TA - ( ( SAL - TS ) / 120 % RTP Span ) x 100% Span a 7.50 % Span Margin
- TA - CSA' a 2.78 % Span Se a { SD 4 SCA) ) C 0.00 + 0.00 ) 0 0.00 % Span A' (PMA:) 2
+ (PMA2) 2
+ (PEA) 2 + (STE) 2 + (SPE)2 + (RTE) 2 (1.67)3 + (4.17)2 + (0.00)2 + (0.00)2 + (0.00)2 + (0.83)2 20.87 % Span Z# aa 1 (A') 2 + r.A + Biases (20.87)1'2 + 0.00 + 0.00 ,, 4.57 % Span R' - T' is the lesser oft T' - { RD + RCA) a ( 1.00 + 0.50 ) U 1.50 % Span Ta* m TA' - S' - Z# - 7.50 - 0.00 - 4.57 a 2.93 % Span IV"' I TS + I TP'/100%Span ] x 120'1RTP ) 0 110.80 % RTP The above-computed AV, is slightly less than that allowed by FCQL-355 (given current Tech Spec requirements of TA - 7.5 %Span, Z a 4.56 %Span, S a 0.00 %Span and AV <
111.1 % RTP, with a CSA of 4.9 %Span). Since TA', Z', and S' remain at current Tech Spec values and since CSA' has been slightly reduced (primarily due to elimination of the originally assumed 0.25 %Span ~) rack comparator setting accuracy [RCSA]), the above-computed value for R' can be increased to the original trigger term T of 1.75 %Span (to retain the original AV). This increase to retain the original "V is justified given that no PUR/SGR hardware changes are proposed for the Power Range NIS channels; channels will be scaled
CALCULATION NO. HNP-I/INST-1010 PAGE 27 REV. 0 TABLE 3-1A (Cont'd) POWER RANGE, NEUTRON FLUX - HIGH SETPOINT SunMiary of CSA and Five-Column Tech Spec Terms co=ensurate for the increased RTP (consistent with the detectors' increased output). A comparison of current and post-PUR/SGR values are summarized as follows: Tech Spec Term Current Tech Spec Value PoSt-PURISGR Value Total Allowance (TA) 7.5 % Span 7.5 % Span Z Term 4.56 % Span 4.56 % Span Sensor Error (S) 0.0 % Span 0.0 % Span Trip Setpoint (TS) < 109.0 % RTP < 109.0 % RTP Allowable Value (AV) < 111.1 % RTP < 111.1 % ATP
CALCULATION NO. HNP-I/INST-1010 PAGE 28 REV. 0 TABLE 3-1B POWER RANGE, NEUTRON FLUX - LOW SETPOINT Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA' - [ (PA 1 )" + (PHA, * (PEA)Z + (SHWE + SD) 2 + (STE)2 + (SPE) 2 + 2 2 (SCA + S?4TE)2 + (SRA) + (RMTE + RD)a + (RTE) + (RCA + FMTE) 2 1112
- [ (1.67)2 + (4.17)2 + (0.00)2 + (0.00 + 0.00)2 + (0.00)2 + (0.00)2 +
(0.00 + 0.00)2 + (0.00)2 + (0.05 + 1.00)2 + (0.83)2 + (0.50 + 0.05)2 2312
- 4.72 % Span [Reference 2.9.g & Reference 2.8 (WCAP Table 3-1)]
Note that all sensor uncertainties are set to zero (similar to the Power Range NIS High Setpoint), owing to channel normalization based upon daily power calorimetric surveillance [and adjustment (as required)] or based upon STE accounted for through PMA neutron flux effects uncertainty. TS - 25.0 % RTP (Reference 2.13.a (UFAPPD, Table 2.2)) SAL m 35.0 %; RTP [Reference 2.13.a (UFAPPD, Table 2.2)] TA I ( TS - SAL ) / 120 % RTP Span ) x 100 % Span ,, 8.33 % Span Margin - TA - CSA' - 3.61 %, Span S' - (SD + SCA ) ,- ( 0.00 + 0.00 ) , 0.00 % Span A' (jAJ)2 + (P4A2) 2 + (PEA) 2 + (STE) 2 + (SPE)2 * (RTE) 2 (1.67)3 + (4.17)2 + (0.00)2 + (0.00)2 + (0.00)2 + (0.83)2 20.87 %' Span Z" - (A')"12 + EA + Biases
, (2D.87)12 + 0.00 + 0.00 a 4.57 % Span T' is the lesser of:
- (RD + RCA) - { 1.00 + 0.50 ) U 1.50 % Span TAO - S- - Z' ,, 8.33 - 0.00 - 4.57 U 3.76 % Span AV' - ( TS + I Ti"/100%SpaSn 3 x 120%RTP ) a 26.80 % RTP The above-computed AV' is slightly less than that allowed by FCQL-355 (given current Tech Spec requirements of TA a 8.33 %Span, Z w 4.56 %Span, S a 0.00 %Span and AV <
27.1 % RTP, with a CSA of 4.9 %Span). Since TA', Z', and S' remain at current Tech Spec values and since CSA' has been slightly reduced (primarily due to elimination of the originally assumed 0.25 %Span rack comparator setting accuracy [RCSA]), the above-computed value for R" can be increased to the original trigger term T of 1.75 %Span (to retain the original AV and for consistency with the Power Range NIS High Setpoint). This increase to
CALCULATION NO. HNP-I/INST-1010 PAGE 29 REV. 0 TABLE 3-1B (Cont'd) POWER RANGE, NEUTRON FLUX - LOW SETPOINT Sunmary of CS. and Five-Colun Tech Spec Terms retain the original AV is justified given that no PURISGR hardware changes are proposed for the Power Range NIS channelst channels will be scaled c-mmensurate for the increased RTP (consistent with the detectors' increased output). A comparison of current and post-PUR/SCR values are summarized as follows: Tech Spec Term Current Tech Spec Value Post-PIR/SOR Value Total Allowance (TA) 8.3 % Span 8.3 % Span Z Term 4.56 %& Span 4.56 % Span Sensor Error (5) 0.0 % Span 0.0 % Span Trip Setpoint (TS) < 25.0 % RTP < 25.0 % RTP Allowable Value (AV) < 27.1 % RTP < 27.1 % RTP
CALCULATION NO. HNP-I/XNST-1010 PAGE 30 REV. 0 TABLE 3-2A POWER RANGE, NEUTRON FLUX - HIGH NEGATIVE RATE Sunmary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA' - [ (PMA) 2 4 (PEA) 2 + (SMTE + SD) 2 + (STE)2 + (SPE) 2 + 2 (SCA + SMTE) 2 + (SRA) 2
+ (RHTE + RD)2 + (RTE) 2
+ (RCA + RMTE) 312
- [ (0.00)3 + (0.00)2 + (0.00 + 0.00)2 + (0.00)2 + (0.00)2 +
(0.00 + 0.00)2 + (0.00)2 + (0.10 + 1.00)2 + (0.83)2 + (0.50 + 0.10)2 ]112
- 1.45 % Span (Reference 2.9.g & Reference 2.8 (WCAP Table 3-2))
Note that all sensor uncertainties are set to zero, owing to the use of a rate (de-rivative) function to eliminate steady-state measurement errors. TS - 5.0 % RTP [Reference 2.13.a (UFAPPD, Table 2.2)] SAL' - 8.0 % RTP [Reference 2.13.a (tUFAPD, Table 2.2)] TA' - ( (SAL' - TS ) / 120 % RTP Span ) x 100 Span - 2.50 % Span Margin - TA' - CSA' - 1.05 % Span S' - {SD + SCA ) U { 0.00 + 0.00 ) m 0.00 % Span A' n (PMA) 2
+ (PEA) 2
+ (STE)2 + (SPE) 2 + (RTE) 2 U
(0.00)2 + (0.00)2 + (0.00)2 + (0.00)2 + (0.83)2 U 0.69 % Span z - (k.)1,2 - rA
- D÷ wasi
- (0.69)112 + 0.00 + 0.00 - 0.83 % Span RI - T' ins the lesser of:
Tj r - (RD + RCA) U ( 1.00 + 0.50 ) U 1.50 % Span T2 " i TA' - S' - Z' 2.50 - 0.00 - 0.83 U 1.67 % Span AV' - ( TS + I T1 "/100%Span ] x 120%RTP ) w 6.80 % RTP The above-computed AV' is greater than that allowed by FCQL-355 (given current Tech Spec requirements of TA - 1.6 %Span, Z - 0.5 %Span, S a 0.0 %Span and AV < 6.3 % RTP, with a CSA of 1.4 %Span). Therefore, the original AV < 6.3 % RTP-should continue to be used within existing MSTs, given its trigger of l.1 %Span. TA' and Z' have been increased based upon the larger SAL' value used. No PUR/SGR hardware changes are proposed for the Power Range NIS channelsi channels will be
- m* scaled conmuensurate for the increased RTP (consistent with the detectors, increased output).
A comparison of current and post-PUR/SGR values are sunmmarized as follows:
CALCULATION NO. .HP-IX/INST-1010 PAGE 31 REV. 0 TABLE 3-2A (Cont'd) POWER RANGE, NEUTRON FLUX - HIGH NEGATIVE RATE Summary of CSA and Five-Column Tech Spec Terms Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 1.6 % Span 2.5 % Span Z Term 0.5 % Span 0.83 % Span Sensor Error (S) 0.0 % Span 0.0 % Span Trip Setpoint (TS) < 5.0 % RTP < 5.0 % RTP Allowable Value (AV) < 6.3 % RTP < 6.3 % RTP
CAL ULATION NO. HNP-X/INST-1010 PAGE 32 REV. 0 TABLE 3-2B POWER RANGE, NEUTRON FLUX - HIGH POSITIVE RATE Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SCR Tech Spec terms for this trip function. CSA)' - (PMA)2 + (PEA) 2 + (SMTE 4 SD)3 + (STE) 2 + (SPE) 2 + 2 2 2 2 (SCA + SMTE) 2 + (SRA) + (RMTE + RD) + (RTE) + (RCA + RMTE) j112 [ (0.00)2 + (0.00)2 + (0.00 + 0.00)2 + (0.00)2 + (0.00)2 + (0.00 + 0.00)2 + (0.00)2 + (0.10 + 1.00)2 + (0.83)2 + (0.50 + 0.10)2 ]i1,
- 1.45 % Span IReference 2.9.g & Reference 2.8 (WCAP Table 3-2)]
Similar to the High Negative Rate trip function, all sensor uncertainties are set to zero, owing to the use of a rate (derivative) function to eliminate steady-state measurement errors. TS a 5.0 % RTP [Reference 2.1] SAL - N/A [References 2.3 and 2.13.aj TA' - C ( SAL - TS) /120 % RTP Span ) x 100 % Span
- N/At Set to 2.50 %Span (per High Negative Rate trip TA' per Table 3-2A)
Use of High Negative Rate TA (and TA') value is consistent with Reference 2.3 and with current Tech Spec Table 2.2-1. Margin - TA - CSA' W 1.05 % Span S' - ( SD + SCA ) - ( 0.00 + 0.00 ) - 0.00 % Span A' (PMA)2 4 (pEA) 2 + (STE) 2 + (SPE) 2 + CRTZ) 2 U (0.00)2 + (0.00)2 + (0.00)2 + (0.00)2 + (0.83)3 0.69 % Span a" (A')"1 2
+ EA + Biases (0.69)112 + 0.00 + 0.00 N 0.83 %, Span R# - T' is the lesser oft T, - { RD + RCA) ( 1.00 + 0.50 ) 1.50 % Span U
Tz v - TA' - Ss - Z" 2.50 - 0.00 - 0.83 1.67 % Span AV' - ( TS + E T1 "/100%Span I x 120DRTP ) - 6.80 % RTP The above-co=puted AV' is greater than that allowed by FCQL-355 (given current Tech Spec requirements of TA f 1.6 %Span, Z w 0.5 %Span, S a 0.0 %Span, and AV < 6.3 % RTP, with a CSA of 1.4 %Span); therefore, the original AV < 6.3 % RTP should be retained within existing MSTs, given its trigger of 1.1 %Span. Since the High Negative Rate SAL' value has been increased, the High Positive Rate TA and Z terms can be increased for post-PUR/SGR values (for consistency). No PUR/SGR hardware
CALCULATION NO. MIP-I/INST-1010 PAGE 33 REV. 0 TABLE 3-2B (Cont'd) POWER RANGE, NEUTRON FLUX - HIGH POSITIVE RATE Summary of CSA and Five-Column Tech Spec Terms changes are proposed for the Power Range NIS channels; channels will be scaled commnsurate for the increased RTP (consistent with the detectors' increased output). A comparison of current and post-PUR/SGR values are summarized as follows: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 1.6 % Span 2.5 % Span Z Term 0.5 % Span 0.83 % Span Sensor Error (S) 0.0 % Span 0.0 % Span Trip Setpoint (TS) < 5.0 % RTP < 5.0 % RTP Allowable Value (AV) < 6.3 % RTP < 6.3 % RTP
CALCULATION NO. HNP-I/INST-1010 PAGE 34 REV. 0 TABLE 3-3 INTERMEDIATE RANGE, NEUTRON FLUX Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for rost-PUR/SGR Tech Spec terms for this trip function. CSAP - [ (PHA) + (pEA)2 + (SMTE + SD)2 + (STE) 2 + (SPE)2 + 2 (SCA + SMTE)2 + (SRA) + (RMTE + RD) + (RTE)2 + (RCA + RHTZ)' ]1/2 2 [ (8.33)' + (0.00)' + (0.00 + 0.00)2 + (0.00)2 0 (0.00)2 + (0.00 + 0.00)' + (0.00)' + (0.10 + 4.20)2 + (1.18)2 + (2.00 + 0.10)) ]112
- 9.68 % Span [Reference 2.9.h & Reference 2.8 (WCAP Table 3-3)]
Note that sensor uncertainties are considered as zero, due to channel normalization (per power calorimetrics) or through inclusion of neutron flux measurement uncertainties within the process measurement accuracy (PMA) term. TS - 25.0 % RTP [Reference 2.1] SAL - N/A [Reference 2.31 M SAL - TS M N/Al Set to 17.0 % Span (based on current Tech Spec TA). margin a TA" - CSA' - 7.32 % Span S' W ( SD + SCA ) - ( 0.00 + 0.00 ) W 0.00 % Span Ze (A')'"+ . EA - ( (PMA)' + (pEA)' + (SPE)' + (STE)2 + (RTE)' ),12 + EA { (8.33)' + 02 ' 0' + 02 + (1.18)2 )112 + 0 - 8.413 % Span R* - T' is the lesser oft TjL - (RD + RCA) - { 4.20 + 2.00 ) - 6.20 % Span TZ" a TA' - St - Z'
- 17.00 - 0.00 - 8.41 a 8.59 % Span AV' a ( TS + I R3/100%Span ] x 120%RTP ) - 32.44 % RTP The above-computed AV' is higher than that allowed by FCQL-355 (given current Tech Spec requirements of Z P 8.41 %Span, T = 5.00 %Span, and AV < 30.9 % RTP, with a CSA of 9.8 %Span). Therefore, since no PUR/SGR hardware changes are proposed for the Intermediate Range NIS channels, the current AV shall be retained.
Channels will be scaled commensurate for the increased RTP (consistent with the detectors' increased output). A comparison of current and post-PUR/SCR values are summarized as follows:
CALCULATION NO. ENP-XI/NST-1010 PAGE 35 REV. 0 TABLE 3-3 (Cont'd) INTERMEDIATE RANGE, NEUTRON FLUX Summary of CSA and Five-Column Tech Spec Terms Tech Spec Term Current Tech Spec Value Post-PURISOR Value Total Allowance (TA) 17.0 % Span 17.0 % Span Z Term 8.41 % Span 8.41 % Span Sensor Error (S) 0.0 % Span 0.0 % Span Trip Setpoint CTS) < 25.0 % RTP < 25.0 % RTP Allowable Value (AV) < 30.9 % RTP < 30.9 % RTP
CALCULATION NO. HNP-I/INST-1010 PAGE 36 REV. 0 TABLE 3-4 SOURCE RANGE, NEUTRON FLUX Sumary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA' - [ (PMA)3 + (PEA) + (SMTZ + SD)2 + (STE)P + (SPZ)3 + (SCA + SMTE) 2 + (SRA) 2 + (P=TE + RD) 2 + (RTE) 2 + (RCA + RMTE) 2 ]1/2
- [ (10.00)2 + (0.00)3 + (0.00 + 0.00)2 + (0.00)2 + (0.00)2, 2
(0.00 + 0.00)2 + (0.00)2 + (0.50 + 3.00) + (0.50)3 + (0.50 + 0.50)2 1112
- 10.65 % Span [Reference 2.9.1 & Reference 2.8 (WCAP Table 3-4)0 Note that sensor uncertainties are considered as zero, due to channel normalization (per power calorimetrics) or through inclusion of neutron flux measurement uncertainties within the process measurement accuracy (PMA) term.
TS - 1.0 x 105 CPS [Reference 2.11 SAL a NIA (Reference 2.3] TAP - SAL - TS
- N/Al Set to 17.0 % Span (based on current Tech Spec TA).
Margin
- TA' - CSA" - 6.35 % Span S' (CSD + SCA ) a { 0.00 + 0.00 ) - 0.00 % Span Z' (A')" 2
+ EA 0 ( (PMA) 2 + (pA)2 + (SpE) 2 + (STE) 2 + (RTE) )1/2 + ZA
{ (10.00)2 , 02 , 02 + 02 + (0.50)2 )112 + 0 a 10.01 % Span RI - T' is the lesser oft TIP - (RD + RCA) - {3.00 + 0.50 ) - 3.50 % Span T21 W TAP - S' - Z' - 17.00 - 0.00 - 10.01 - 6.99 % Span AV' ({TS + [ R'/100%Span ] x 1.0 x l0o CPS ) - 1.35 x 10' CPS The above-computed AV' is comparable to that allowed by FCQL-355 (given current Tech Spec requirements of Z = 17.0 %Span, T w 3.8 %Span, and AV < 1.4 x 10' CPS, with a CSA of 10.7 %Span). Therefore, since no PUR/SGR hardware changes are proposed for the Source Range NIS channels, the current AV shall be retained. Channels will be scaled conmensurate for the increased CPS (consistent with the channels' increased output). A comparison of current and post-PUR/SGR values are summarized as follows:
CALCULATION NO. HNP-XI/NST-1010 PAGE 37 REV. 0 TABLE 3-4 (Cont'd) SOURCE RANGE, NEUTRON FLUX Summary of CSA and Five-Column Tech Spec Terms Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 17.0 % Span 17.0 % Span Z Term 10.01 % Span 10.01 % Span Sensor Error (S) 0.0 % Span 0.0 % Span Trip Setpoint (TS) < 1.0 x 10' CPS < 1.0 x 10s CPS Allowable Value (AV) < 1.4 x 103 CPS < 1.4 x 10s CPS
CALCULKTION NO. MNP-I/INST-1010 PAGE 38 REV. 0 TABLE 3-5 OVERTEMPERATURE AT Sunmary of CSA and Five-Column Tech Spec Terms The setpoint for the Overtemperature AT trip function is based upon the equation as specified in the current Tech Spec Table 2.2-1. For PUR/SGR operation, the trip function coefficients and time constants were updated, based upon the joint Westinghouse/Siemens analyses (including that documented per Reference 2.10.f [COL-99-105, Rev. 1]). These updated values are contained within ONote 10 of the Tech Spec mark-up (included in Table 4-1 herein). Owing to the complex function and its associated hardware implementation (which uses AT channel inputs along with compensation from Pressurizer Pressure, Power Range HIS AX, and Tavg), discrete allowable values have been compruted (by Westinghouse, per Reference 2.9.b [cN-TSS-98-33, Rev. 11) to correlate to each of these channel inputs. This computational practice reflects actual [MST] surveillance calibration tolerances; these Westinghouse proposed allowable values have been adjusted/recon-ciled herein (for consistency with other RTS/ESFAS trip functions), and the updated values are contained within "Note 2" of the Tech Spec mark-up (included in Table 4-1 herein). Xn lieu of current use of a single Allowable Value for the overall channel, the use of discrete allowable values (for each of these inputs) satisfies NRC requirements for fixed Allowable Value requirement, and is consistent with Westinghouse recommendations within Reference 2.1l.a. Post-PUR/SGR Tech Spec terms can be computed, by solving for the equations generally shown per Table 1-2 herein. Uncertainties calculated in Reference 2.8 (Table 3-22) and Reference 2.9.b are based upon the normalization of AT, (performed per ZPT-156). CSA' - 8.38% of AT span [Ref. 2.9.b, Page 26 & Ref. 2.8 (Table 3-5)] This CSA' consists of: Process Measurement Accuracy terms (noted on Pages 20, 21, 23, and 25 of Ref. 2.9.b); RCS N-R RTD and pressurizer pressure transmitter uncer-tainties, R/E conversion and nonlinearity rack uncertainties; as well as other process rack uncertainties for AT, Tavg, pressurizer pressure, and AI channels. TS' - 1.185 KX nominal and SAL' - 1.32 Kj maximum [Ref. 2.9.b, Pages 20 & 26] TA' - ( (K1max-XLnom) x (TxOu."-Tcol.,,) / (AT Span at 15 0% Power) ) x 100D% Span
- { (1.32 -1.185) x (620.2 - 557.4) / (94.2) ) x 100% Span U 9.00% of AT span [Ref. 2.9.b, Page 26]
Margin 0 TA" - CSA' a 0.62% of AT span [Ref. 2.9.b, Page 263 Comparable S', R', and Z' terms can be defined using the lcsal" [above CSA'] rela-tionship on Page 26 of Ref. 2.9.b, by discretely recognizing each of the CSA' compo-nents (noted above); note that S' and R' terms can be computed for the inputs to this AT trip function, using Table 1-2 methodology. (Terminology and values are shown consistent with those obtained from Ref. 2.9.b.) S'pressure - Variation of (Sprz)112 per Ref. 2.9.b, Page 25
- ( (sdpps) + (scaps) ) x Conv2 a ( (1.00) + (0.50) ) x 0.64 i 1.50% of pressurizer pressure span x 0.64 % DT span/% pressure span
- 0.96% of AT span -- 1.0%of AT span
CALCULATION NO. WNP-IXINST-1010 PAGE 39 REV. 0 TABLE 3-5 (Cont'd) OVERTEMPERATURE AT Summary of CSA and Five-Column Tech Spec Terms S temporature M (SA*O)12 , 0.25% of AT span [Ref. 2.9.b, Page 251 Note the above S'tweprature value is lower than its original Tech Spec temperature sensor error, since Reference 2.9.b RTD uncertainties (e.g., scartd, smtertd, and sdrtd) are set to zero due to normalization process. Since RTD cross-calibrations are performed prior to channel normalization, further acceptance criterion is re-quired to define each RTD's acceptability. Reference 2.4.e [INST-1049], Section 6.2 allows for a < 1.2'? temperature accuracy for each Tbo or TooId RTD (based upon a 0.50F RTD calibration accuracy and a 0.70? 18-month RTD drift [as confirmed by the RTD cross-calibration procedure EST-1041). This can be translated into a Tech Spec sensor error of 1.3% of AT span [by ([1.2'? error/94.2*r AT span] x 100%) - 1.27 % AT span]. Round-up allows for the possibility of a slightly lower AT span (e.g., -90'? AT at current plant levels with SG replacement). As noted above, Allowable Values for AT, Tavg, pressurizer pressure, and AZ channels [in terms of AT spani as well as pressurizer pressure transmitter Operability Limit tin terms of % of pressure span] have been recomputed (from those shown on Ref. 2.9.b, Page 26), based upon the following uncertainty terms (using Ref. 2.9.b terminology and values [including conversions shown in Ref. 2.9.b, Page 25])s
- RackAVAT - {(dtrd) + (dt :rcal) 3
" ( (1.0) + (0 '.35) o R'*TA 1.35% of AT span -- 1.4% of AT span RackAVTayg - ((Tavg.rd) + (CTavg.rca)) x Conv3
- { (1.0) + (0.35) ) x 1.493
- 2.015% of AT span -- 2.0% of AT span R* prz - RackAVprx - {(rrdps) + (rcal-ps)) x Conv2
- ( (0.5) + (0.1)) x 0.64L
- 0.384% of AT span -- 0.4% of AT span
- RackAVAI - t(rrdAl) + (rcalAZ)) x Conv4
( (0.5) + (0.1) ) x 1.2
- 0.72% of AT span -- 0.7% of AT span #prressuro M Operableprttrans - 1.5% of pressurizer pressure span EPT-156 (performed each calendar quarter) will assure that AT trip channels are maintained in a normalized condition. A -1% AT tolerance is used as the limiting EPT-156 acceptance criterion [to preclude the need for renormalization], which is comparable to the above-noted AT channel input rack drift.
Furthermore, Tech Spec term Z' can be calculated using the (Ap)uI2 + Biases equation, per the following determination (based upon the terminology within Ref. 2.9.b): A' a 2 2 2 (PMA) + (PEA) + (STE)2 + (SPE) + (RTE)2 2
)2 + 2 where: PMA - { (pmaTb) + (pma&1_1)2 + (PimaA_ 2 (pmu~,,, 1 0 l) }1/2 PM& - ( (0.00)2 + (3.00)2 + (1.30)2 + (1.33)2 )1*2 - 3.53 %sAT span
CALCULATION NO. HNP-I/XNST-1010 PAGE 40 REV. 0 TABLE 3-5 (Cont'd) OVERTEMPERATURE AT SummEry of CSA and Five-Column Tech Spec Terms which accounts for all random process measurement effects (i.e., AT Hot Leg streaming (Th], incore/excore mismatch [AX_1], incore map AZ uncertainty [AI_2], and secondary side calorimetric uncertainty present at normalization [pwrcal]), after conversion to % AT span [per Ref. 2.9.b, Page 23]. PEA and SPE - 0, since these components are not specified within Ref. 2.9.b. STE wste B steps x Conv2 w 1.4375 x 0.64 a 0.92 % AT span [per Ref. 2.9.b, Pages 22 & 24] RTE a dtrte - 0.5 % AT span [per Ref. 2.9.b, Page 21] Therefore, A' - (3.53)2 + (0.00)2 + (0.92)2 + (0.00)3 + (0.50)2 - 13.5573 % AT span In addition, all PMA terms treated as Biases have been included (i.e., the AT burndown effect tbudtl, the Tavg burndown effect [butavg], the Tavg asymmetry [Tavg asym], and the T' - Tref mismatch [TpTr]l per Ref. 2.9.b, Page 20 defines these terms as biases, and Page 23 provides conversions in terms of % AT span): Biases -(pa *..*) *+ (pma.v_) + m .) + (Prza*_,)
- (0.64) + (0.45) + (1.49) + (1.05) n 3.63 % AT span Therefore, Z' can be solved based on the above determined A' and Biases:
Z' 0 (A')'" + Biases - (13.5573)112 + 3.63 a 7.312 -i 7.31 '% AT span Note that this computed Z' term is slightly larger than the previous Tech Spec value, for consistency with the PUR/SGR uncertainty calculation and its associated uncertainty component accounting. Tech Spec terms can be sumuarized as followsn Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 8.7 '%Span 9.0 % Span Z Term 6.02 % Span 7.31 % Span Sensor Error (S) Per current Note 5 Per new Note 5 (see below) Trip Setpoint (TS) Per current Note I Per new Note 1 (see below) Allowable Value (AV) Per current Note 2 Per new Note 2 (see below) Post-PUR/SGR Note It Overtemperature AT Function, Coefficients, and Time Constants will be updated consistent with format specified in References 2.9.b and 2.10.f. See Tech Spec mark-up contained in Table 4-1 herein. Post-PUR/SGR Note 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than: 1.4% of AT span for AT
CALCULATION NO. .Mq-X/XNST-101O PAGE 41. REV. 0 TABLE 3-5 (Cont'd) OVERTEMPERATURE AT Summary of CSA and Five-Column Tech Spec Terms channel input; 2.0% of AT span for Tavg input; 0.4'% of AT span for pressurizer pressure input; and 0.7% of AT span for the Al input. Post-PUR/SGR Note 5S The sensor error is: 1.3% of AT span for AT/Tavg temperature measurements; and 1.0% of AT span for pressurizer pressure measurements.
CALCUL&TION NO. ENP-I/INST-1010 PAGE 42 REV. 0 TABLE 3-6 OVERPOWER AT Summary of CSA and Five-Column Tech Spec Terms The setpoint for the Overpower AT trip function is based upon the equation as specified in the current Tech Spec Table 2.2-1. For PURISGR operation, the trip function coefficients and time constants were updated, based upon the joint Westinghouse/Siemens analyses (including that documented per Reference 2.10.f [CQL-99-105, Rev. 1]). These updated values are contained within -Note 3" of the Tech Spec mark-up (included in Table 4-1 herein). Owing to the complex function and its associated hardware implementation (which uses AT channel inputs along with compensation from Tavg), discrete allowable values have been conputed (by Westinghouse, per Reference 2.9.b [CN-TSS-98-33, Rev. 1)) to correlate to each of these channel inputs. This computational practice reflects actual [MST] surveillance calibration tolerances; these Westinghouse proposed allowable values have been adjusted/reconciled herein (for consistency with other RTS/ESFAS trip functions), and the updated values are contained within "Note 4" of the Tech Spec mark-up (included in Table 4-1 herein). Similar to that noted in Table 3-5 herein, the use of discrete allowable values (for each of these inputs) satisfies NRC requirements for fixed Allowable Value requirement, and is consistent with Westinghouse recosmmendations within Reference 2.11.a. Lm/ Post-PUR/SGR Tech Spec terms can be computed, by solving for the equations generally shown per Table 1-2 herein. Uncertainties calculated in Reference 2.8 (Table 3-22) and Reference 2.9.b are based upon the normalization of AT, (performed per EPT-156). CSA' - 2.95% of AT span (Ref. 2.9.b, Page 32 & Ref. 2.8 (Table 3-6)1 This CSA' consists of: Process Measurement Accuracy terms (noted on Pages 20, 21, 23, and 25 of Ref. 2.9.b)l RCS N-R RTD uncertainties; R/E conversion and non-linearity rack uncertainties; as well as other process rack uncertainties for AT and Tavg channels. TS - 1.12 K4 nominal and SAL' m 1.18 K4 maximum (Ref. 2.9.b, Pages 28 & 32) TA' u { (Komax-K 4nom) c (Tx.%L.-Tcoa.1 ) / (AT Span at 150%' Power) ) x 100% Span
- ((.18- 1.12) x (620.2 - 557.4) / (94.2) ) x l00% Span a 4.00% of AT span [Ref. 2.9.b, Page 32]
Margin M TA' - CSA' & 1.05% of AT span (Ref. 2.9.b, Page 32] Comparable S', R', and Z' terms can be defined using the Ocsalo [above CSA'3 rela-tionship on Page 32 of Ref. 2.9.b, by discretely recognizing each of the CSA' compo-nents (noted above); note that $' and R' terms can be computed for the inputs to this AT trip function. (Terminology and values are shown consistent with those obtained from Ref. 2.9.b.) S'temperature M (SRTD) 1 /2 o 0.25% of AT span [Ref. 2.9.b, Page 31] As discussed in Table 3-5 herein, the 1.3% AT span acceptance criterion is also applicable (prior to channel normalization) to define the RTDS' OPAT Tech Spec sensor error S' term, in lieu of the (already normalized) above-noted S'tenverature-
CALCUILTION NO. ENP-I/INST-1010 PAGE 43 REV. 0 TABLE 3-6 (Cont'd) OVERPOWER AT Summary of CSA and Five-Column Tech Spec Terms As noted above, Allowable Values for AT and Tavg channels [in terms of AT span] have been recomputed (from those shown on Ref. 2.9.b, Page 32), based upon the following uncertainty terms (using terminology and values obtained from Ref. 2.9.b [including the OPAT "Conv2l conversion factor specified on Page 31 of Ref. 2.9.b]): RackAVAT - { (dtrd) + (dtrcal))
- ( (1.0) + (0.35) )
- 1.35% of AT span -- 1.4% of AT span R'Ta&V - RackKVTfT* = ((Tavg.rd) + (Tavgrca)) x [OPATConv2J
- { (1.0) + (0.35) xc 0.133 S D0.179% of AT span -m 0.2% of AT span As noted in Table 3-5, limiting EPT-156 renormalization criterion assures channel normalization comparable to the above-computed AT channel input rack drift.
Also similar to the process shown in Table 3-5, Tech Spec term Z' can be calculated using the (A') 11 2 + Biases equation, per the following OPAT determination (based upon the terminology and % AT span conversions, respectively, within Ref. 2.9.b, Pages 28 and 30)t A' M (PMA) 2 + (PEA) 2 + (STE) 2
+ (SPE) 2 + (RTE) 2 where: PMA - ( (pma'n) 2
+ 2 o*113 PHA s ( (0.00)3 + (1.33)2 )112 - 1.33 % AT span which accounts for all random process measurement effects (i.e., AT Hot Leg streaming [Th], and secondary side calorimetric uncertainty present at normalization tpwr.cal]), after conversion to % AT span [per Ref. 2.9.b, Pag*e 303.
PEA, STE, and SPE - 0, since these components are not specified within Ref. 2.9.b. RTE - dtrte - 0.5 % AT span [per Ref. 2.9.b, Page 21] Therefore, A' a (1.33)2 + (0.00)2 + (0.00)2 + (0.00)2 + (0.50)2 - 2.0189 % AT span in addition, all PHA terms treated as Biases have been included (i.e., the AT burndown effect [budt], the Tavg burndown effect [butavg], the Tavg asymmetry [Tavgasym], and the T' - Tref mismatch [TpTr]I per Ref. 2.9.b, Page 28 defines these terms as biases, and Page 30 provides [OPAT] conversions in terms of % AT span) : Biases - (pmaf) + (pma*b.,) + (pma,.,.. 1) + (pma1 .%,,) a (0.64) + (0.04) + (0.13) + (0.09) - 0.90 %' AT span Therefore, Z" can be solved based on the above determined A' and Biases: 2 Z" (A')11 + Biases - (2.0189)1'2 + 0.90 - 2.3208 -- 2.32 % AT span
CALCULATION NO. HNP-I/INST-1010 PAGE 44 REV. 0 TABLE 3-6 (Cont'd) OVERPOWER AT Summary of CSA and Five-Column Tech Spec Terms Note that this computed Z". term is slightly larger than the previous Tech Spec value, for consistency with the PUR/SGR uncertainty calculation and its associated uncertainty component accounting. In summary, Tech Spec terms can be summarized as follows: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 4.7 % Span 4.0 % Span Z Term 1.50 % Span 2.32 % Span Sensor Error ({) 1.9 % Span 1.3 % Span Trip Setpoint (TS) Per current Note 3 Per new Note 3 (see below) Allowable Value (AV) Per current Note 4 Per new Note 4 (see below) Post-PUR/SGR Note 3: Overpower AT Function, Coefficients, and Time Constants will be updated consistent with format specified in References 2.9.b and 2.10.f. See Tech Spec mark-up contained in Table 4-1 herein. Post-PUR/SGR Note 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than: 1.4% of AT span for AT inputi and 0.2% of AT span for Tavg input.
CALCULATION NO. HNP-IIINST-1010 PAGE 45 REV. 0 TABLE 3-7A PRESSURIZER PRESSURE - LOW, REACTOR TRIP Suimnary of CSA and Five-Column Tech Spec Term-s Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA' - [ (PMA)2 + (PEA) 2 + (SMTE + SD) 2 + (STE)' 2 (SPE)' + (SCA + S=TS)2 + (SEA)2 + (p=TE + RD)2 + (RTE)2 + (RCA + pMTE)2 ]112 [ (0.00)2 + (0.00)2 + (0.71 + 1.00)2 + (1.44)2 + (0.00)2 + (0.50 + 0.71)2 + (0.25)' + (0.50 + 1.00)2 + (0.50)' + (0.50 + 0.50)' 31t2 3.16 % Span [Reference 2.9.c & Reference 2.8 (WCAP Table 3-7)] TS - 1960 psig MReference 2.13.a (UFAPPD, Table 2.2)1 SAL - 1920 psig [Reference 2.13.a (UPAPPD, Table 2.2)3 TA (TS - SAL) /800 psig Span ) x 100 % Span M 5.00 % Span Margin - TA - CSA' 1.84 % Span S' { (SD) f + (SCA) - { (1.0) + (0.5) ) 1.50 % Span Z , (A,)1'2 + EA CC (PMA) 2 + (PEA) 2 + (SPE)a + (STE) 2
+ (RTE)2 )112 + EA
- { 02 + 02 + 02, (1.44)2 + (0.50)' )112 + 0.00 W 1.522 % Span R' - T' is the lesser of:
T' { RD + RCA 3 - { (1.0) + (0.5) 3 - 1.50 % Span T" TA - S'- ' 5.00 - 1.50 -1.52 0 1.98 % Span AVe ( TS - [ R'/100%'Span ] x 800 psig M 2.945 pisg The above-computed AV' is comparable to the originally 1946 psig value specified by FCQL-355 (with current Tech Spec requirements of Z n 2.21 %Span, T a 1.8 %Span, and S - 1.5 %Span, based upon a CSA of 3.9 %Span). Given the reduction in CSA', Z', and T', the computed AV' will be used for post-PUR/SGR Allowable Value. A comparison of current and post-PUR/SCR values are surmarized as follows: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 5.0 % Span 5.0 % Span Z Term 2.21 % Span 1.52 % Span Sensor Error (S) 1.5 % Span 1.5 % Span Trip Setpoint (TS) > 1960 psig > 1960 psig Allowable Value (AV) > 1946 psig > 1948 psig
CALCULATION NO. HNP-I/INST-1010 PAGE 46 REV. 0 TABLE 3-7B PRESSURIZER PRESSURE - HIGH, REACTOR TRIP Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA" [ (PHA)2 + (PEA) 2 + (SMET + SD)3 + (STE) 2 + (SPEl) + 2 (SCA + SMTE) + (SRA) 2
+ (RMTE + RD))3 + (RTE) + (RCA + RMTE) 23]a1
- [ (0.00)2 + (0.00)2 + (0.71 + 1.00)2 + (1.44)2 + (0.00)2 +
(0.50 + 0.71)2 + (0.25)2 + (0.50 + 1.00)2 + (0.50)2 + (0.50 + 0.50)2 ]12
- 3.16 % Span [Reference 2.9.c & Reference 2.8 (WCAP Table 3-7)]
TS - 2385 psig [Reference 2.13.a (UFAPPD, Table 2.2)] SAL - 2445 psig [Reference 2.13.a (UFAPPD, Table 2.2)1 TA W ( (SAL - TS /800 psig Span ) x 100 % Span W 7.50 % Span Margin - TA - CSA' - 4.34
- Span S' - j (SD) + (SCA)) (1.0)
( + (0.5)) 1.50 Span Z#' - (A.')1 2 + EA - ( (PMA) + (PZA)E + (SPE)2 + (STE)2 + (RTE) }2. + ZA
- ( 02 + 02 + 02 + (1.44)2 + (0.50)2 )212 + 0.00 - 1.522 % Span R' w T' is the lesser of:
T11 { RD + RCA ) - ( (1.0) + (0.5) ) - 1.50 % Span T2 ' - TA" - '- Z' u 7.50 - 1.50 - 1.52 W 4.48 % Span Av W ( TS + [ R'/100%Span I x 800 psig s- 2397 psig The above-computed AV' is comparable to the originally 2399 psig value specified by FCQL-355 (with current Tech Spec requirements of Z a 5.01 %Span, T - 1.8 %.Span, and S - 0.5 %Span, based upon a CSA of 6.3 %Span). Given the reduction in CSA', Z', and T', the computed AV' will be used for post-PuR/SGR Allowable Value. A comparison of current and post-PUR/SGR values are summarized as follows: Tech Spec Term Current Tech Spec Value Post-PtUR/SGR Value Total Allowance (TA) 7.5 % Span 7.5 % Span Z Term 5.01 % Span 1.52 % Span Sensor Error (S) 0.5 % Span 1.5 % Span Trip Setpoint (TS) < 2385 psig < 2385 psig Allowable Value (AV) < 2399 psig < 2397 psig
CALCULATION NO. HNP-X/INST-1010 PAGE 47 REV. 0 TABLE 3-9 REACTOR COOLANT FLOW - LOW Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA' [ (PEA) 2 + (S=T2 + SD)"2 (STE) 2 + (SPE)' + (SCA + 5MT)2 + (SRA)2 + (PMTE + RD)a + (RTE)2 + (RCA + RMTE)z ]"' + PMA,...* + P* %.c n [ (0.00)2 + (0.56 + 1.25)2 + (0.50)2 + (0.50)2 + (0.50 + 0.56)2 + (0.50)2 + (0.20 + 1.00)3 + (0.50)2 + (0.50 + 0.20)2 11'2 + 0.87 + 1.68 M 5.25 % Span [Reference 2.9.d & Reference 2.8 (JCAP Table 3-8)] TS u 92.0 % Level Span [Reference 2.13.a (UFAPPD, Table 2.2)] SAL - 100 % Level Span (based on original FCQL-355 value, that Przr fillso Ref. 2.13.a, Table 2.2 conservatively specifies the current Tech Spec AV] TA - { ( SAL - TS ) / 100 % level ) x 100 % Span 9.0 % Span 8 Margin , TA - CSA' M 2.75 % Span S' - ( (SD) * (SCA)) - { (1.25) + (0.5)) - 1.75 % Span Z' 2 (A')"' + Biases m (PEA) + (SPE)2 + (STE)2 + (RTE))2 1 1 2 + EA + PMAj... ( 0' + (0.5)2 + (0.5)2 + (0.5)2 )12 + 0 + (0.87 + 1.68) - 3.416 % Span Ra = T' is the lesser of: T," {RD + RCA) I , {(1.0) + (0.5)) 1.50 % Span Tar TA" -- SB - #
' 8.00 - 1.75 - 3.42 2.83 % Span AV' * ( TS + [ R'/100%Span 3 x 100 % Level ) a 93.5 % Level Span The above-computed AV' should be used in lieu of the current Tech Spec AV of 93.8 %
level span (owing to the original 1.8% Span trigger value). A comparison of current and post-PUR/SCR values are summarized as follows: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 8.0 % Span 8.0 % Span Z Term 2.18 % Span 3.42 % Span Sensor Error (S) 1.5 % Span 1.75 % Span Trip Setpoint (TS) < 92.0 % level span _ 92.0 % level span Allowable Value (AV) < 93.8 % level span < 93.5 % level span
CALCULATION NO. HNP-I/INST-1010 PAGE 48 REV. 0 TABLE 3-9 REACTOR COOLANT FLOW - LOW Summary of CSA and Five-Column Tech Spec Terms Based upon the equation format shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. In addition, uncertainty components are adjusted for the flow conversion factor of 0.663 (used to convert uncertainties from % DP transmitter span to % RCS flow span), which was computed on Page 21 of Reference 2.9.ul see Reference 2.8, Table 3-24 [AP Measure-ments Expressed in Flow Units] for further derivation of conversion factor. Channel normalization, based upon EST-709 calorimetric measurement and EST-708/0ST-1021 surveillances, allows sensor calibration tolerance [SCA], sensor M&TE [SMTEI, and sensor pressure & temperature effects [SPE & STE] to be defined with zero uncertainty. 2 CSA" [ (PKA1)2 + (PHA2) 2 + (PEA) 2 4 (SMTX + SD) 2 + (STZ) + (SPZ)" + (SRA)3 + (SCA + SMTE) 2
+ (RMTE + RD) + (RTE) + (RCA + RpMTE) 2 1112 + Calorimetric 2 2 Wias
[(0.40)2 + (1.33)2 + (0.33)2 + (0.0 + 0.5)2 + (0.0)2 + (0.0)2 + (0.17)2 + (0.0 + 0.0)2 + (0.33 + 0.66)0 + (0.33)2 + (0.33 + 0.33)2]112 + 0.13 0 2.1 % Flow Span [Reference 2.9.n & Reference 2.8 (WCAP Table 3-9)] TS - 90.5 % RCS Flow [Reference 2.13.a (UFAPPD, Table 2.2)] SAL' - 85.0 % RCS Flow [Reference 2.13.a (UFAPPD, Table 2.2)] TA' - ( (TS - SAL' ) /120 % flow) x 100 % Span - 4.58 % Flow Span Margin m TA - CSA' - 2.48 % Flow Span S' W { (SD) + (SCA)) 0 1 (0.50) + (0.00) )
- 0.50 % Flow Span Z. (A')" 2 + Biases
(( (PLI3M) 2
+ (PHA,)
2
+ (PEA) 2
+ *
(SPE) + (STE) 2 * (RTE) 3} 112 + calorimetric sla
- ( (0.40)2 + (1.33)2 + (0.33)2+ 02 + 02 + (0.33)2 ),1l + (0.13) i 1.602 % Flow Span R' n T' is the lesser of:
T," N ( RD + RCA ) * { (0.666) + (0.333))
- 1.00 % Flow Span T I
-" TAP - S* - Z" W 4.58 - 0.50 - 1.60 - 2.48 % Flow Span Since above computations are already converted to % RCS Flow Span:
AV' m ( TS - R' ) - 89.5 % RCS Flow The aboVe-computed TA' reflects the increased PUR/SGR analytical limit (from the current TA of 2.9% Flow Span). Since Z' and S, values computed are slightly smaller than th* current Tech Spec S and Z terms, it is acceptable to maintain S' - S w 0.60% Flow Span and Z' - Z - 1.98% of Flow Span (based upon the increased TA' term, and given that no PUR/SGR-related hardware changes [other than normalization for new RCS flow conditions at uprated power operation] are being implemented). A compari-son of current and post-PUR/SGR values are summarized as follows:
CALCOLPIXTION NO. EI'-I/XNST-1010 P'AGE 49 REV. 0 TABLE 3-9 (Cont'd) REACTOR COOLANT FLOW - LOW Surmary of CSA and Five-ColumnTech Spec Terms Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 2.9 % Span 4.58 % Span Z Term 1.98 % Span 1.98 % Span Sensor Error (S) 0.6 % Span 0.6 % Span Trip Setpoint (TS) > 90.5 % RCS Flow > 9D.5 % RCS Flow (AV) > 89.5 % RCS Flow > 89.5 % RCS Flow Allowable Value
CALCULATION NO. MNP-I/INST-1010 PAGE 50 REV. 3 TABLE 3-10A SG WATER LEVEL, LOW-LOW (FW LINE BREAK) Sumiary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function.
+ (STE) 2 + 2 2 CSA' - [ (SMTE + SD) (SPE) + (SCA + SMTE) + (SRA) 2 +
(RMTE + RD) 2
+ (RTE)2 + (RCA + RMTE) 2 112÷ + EAR.C,., + EAII +
PMIxUfL*9T,,p + PMAvreasure + PMAuboo1 + PMATIUj4vd*v ÷tyP+AKadpI.t*DP
- [ (0.50 + 1.50)2 + (0.50)2 + (0.63)2 + (0.50 + 0.50)2 + (0.50)2 +
(0.08 + 1.00)2 + (0.50)2 + (0.50 + 0.08)2112 + (1.50) + (10.00) + (0.40) + (0.40) + (1.90) + (0.00) + (2.30)
- 19.27 % Span [References 2.8 (WCAP Table 3-10a), 2.9.a and 2.15)
Note that above CSA' computation includes a 1.5%Span sensor drift uncertainty (ver-sus the 2.0% Span value originally assumed in References 2.8 and 2.9.a), based upon subsequent review of As-FoundlAs-Left transmitter drift data. In addition, no uncertainty [bias) due to cable insulation resistance degradation was assumed above (versus the 1.0% Span value originally assumed in Reference 2.9.a)l this is based upon the short-lived (i.e., less than 30-second) Feedwater Line Break accident environment prior to the reactor trip (for consistency with assumption in INST-1045, Rev. 1, Section 6.10 [Reference 2.4.d3). TS' a 25.0 % Level [Reference 2.13.a (UFAPPD, Table 2.2)] SAL' = 0.0 % Level (Reference 2.13.a (UFAPPD, Table 2.2)3 TA' - ( ( TS' - SAL' ) /100 level ) x 100 % Span 0 25.0D % Span Margin - TA' - CSA' - 5.73 % Span S, ( (SD) + (SCA) ) - ( (1.50) + (0.50)) - 2.00 % Span Z' - (A')1 2
+ Biases 2 2 2
{(SpE)2 + (STE) + (RTE) )" +
÷ ,A*,, + EAML4 ÷
*& PMA%.r&., +
?MApr***wr* + P)zubo1 + PM + PMAeiayj~t*D, 4A
- ((0.63)2 + (0.50)2 + (0.S0)2)1/2 * (1.50) + (10.0) + (0.40) +
(0.40) + (1.90) + (0.00) + (2.30) W 17.45 % Span Note that Biases shown conservatively reflect a worst-case value over the entire instr*uent span, and not specifically at the 25% Level trip setpoint. RI - T' is the lesser of: T;' C RD + RCA ) - ( (1.0) + (0.5) m 1.50 %;Span T20 - TA' - S' - Z" - 25.00 - 2.00 - 17.45 - 5.55 % Span AV' { TS' ( - [ R'/00iSpan I x 100 % Level ) - 23.5 % Level Since the above-noted trip setpoint corresponds to a requirement for the Model A75 replacement steam generators [RSGs], the current Tech Spec values (associated with
CALCULATION NO. PAGE 51 REV. 3 TABLE 3-10A (Cont'd) SG WATER LEVEL, LOW-LOW (FW LINE BREAF) Summary of CSA and Five-Column Tech Spec Terms the Model D-4 SGs) are not directly comparable. The summary which follows (for current and post-PUR/SGR values) has been provided for completeness only: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 19.2 % Span 25.0 % Span Z Term 14.06 % Span 17.45 % Span Sensor Error (S) 2.97 % Span 2.0 % Span Trip Setpoint (TS) > 38.5 % level > 25.0 % level Allowable Value (AV) > 36.5 % level > 23.5 % level Table 3.3-4, Item 6.c [Auxiliary Feedwater Initiationi also specifies the Low-Low SG Level RTS trip setpoint for this XSFAS function. Since the same RTS channels perform this ESFAS function, the above RTS post-PUR/SGR values can be applied to its corresponding ESFAS Tech Spec requirement. (This is consistent with the practice used in the current Tech Spec Table 2.2-1, Item 13 and Table 3.3-4, Item 6.c.)
CALCULATION NO. HNP-I/INST-1010 PAGE 52 REV. 3 TABLE 3-10B SG WATER LEVEL, LOW-LOW (LOSS OF NORMAL FW) Sumuary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA" - [ (SMT= 4 SD)2 + (STE) 2
+ (SPE)2 + (SCA + SMT=)3 + (SRA)a +
2 2 (RMTE + RD) + (RTE) + (RCA + RHTE) I" + EA,.t,.. 4 ZAL, + PMA4*&.gimqp + PMApoesgor + PMAub, 0 ol + PMArluldYeloaity + PH4i1dr1teDP
, [ (0.50 + 1.50)2 + (0.50)2 4 (0.63)2 + (0.50 + 0.50)2 + (0.50)2 +
(0.08 + 1.00)2 + (0.50)3 + (0.50 + 0.08)3 ]112 + (0.00) + (0.00) + (0.40) + (0.40) + (1.90) + (0.00) + (2.30) in 7.77 % Span (References 2.8 (WCAP Table 3-10b), 2.9.a and 2.153 As noted per Table 3-10A, the above CSA' computation includes: a 1.5% Span sensor drift uncertainty (versus the 2.0% Span value originally assumed in References 2.8 and 2.9.a); and conservatively chosen Biases which reflect worst-case values. TS' " 25.0 % Level [Reference 2.13.a (UFAPPD, Table 2.2)3 SAL' - 16.1 % Level [Reference 2.13.a (UPAPPD, Table 2.2)] TAO a ( ( TS' - SAL' ) / 100 % level ) x 100 % Span a 8.9 % Span Margin - TA' - CSA' 1.13 % Span I So - ( (SD) (SCA)) a ( (1.50) + (0.50)) - 2.00 %; Span ZF (A')"I2 + Biases
- ( (SPE) 2 + (STE) 2 + (RTz) ) 12 + zA,.ei.. + rA,,. 4 PMA+t.g +
PMAp,..,IP + + PMA9Ud2 &p+
- ( (0.63)2 + (0.50)2 + (0.50)2 1)' + (0.00) + (0.0) + (0.40) +
(0.40) * (1.90) + (0.00) + (2.30)
- 5.95 %.Span R, w T' is the lesser of:
TIf 0 { RD + RCA) - ( (1.0) + (0.5)) - 1.50 % Span T=r N TA " - S' - Z" - 8.90 - 2.00 - 5.95 a 0.95 % Span I AV' - ( TS' - [ R'/100%Span I x 100 % Level ) - 24.05 % Level I Since the current licensing basis for the Low-Low SG Narrow-Range Level specifies the Tech Spec TA and Z for only the Feedwater Line Break (and not for the Loss of Normal Feedwater condition), the values within Table 3-10A continue to apply for the Low-Low setpoint Tech Spec requirements for TA' and Z'. The summary which follows (for current (Model D-4 SG] and post-PUR/SGR [Model A75 RSG] values) has been provided for completeness only, and is consistent with that shown in Table 3-1OA (absent a specific current Tech Spec listing associated with this channel's function under Loss of Normal Feedwater, and owing to the coumon hardware implementation for these trip functions):
CALCULATION NO. MNP-X/INST-1010 PAGE 53 REV. 3 TABLE 3-10B (Cont'd) SG WATER LEVEL, LOW-LOW (LOSS OF NORMAL FW) Summary of CSA and Five-Column Tech Spec Terms Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 19.2 % Span 25.0 % Span Z Term 14.06 % Span 17.45 % Span Sensor Error (S) 2.97 % Span 2.0 % Span Trip Setpoint (TS) : 38.5 % level > 25.0 % level Allowable Value (AV)
- 36.5 % level > 23.5 % level
CALCULATION NO. ENP-I/INST-1010 PACE 54 REV. 3 TABLE 3-10C STEAM GENERATOR WATER LEVEL, LOW Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. 2 CSA' - [ (SMTE + SD) 2 4 (STE) 2 + (SPE) + (SCA + SMTE)2 4 (SRA)3 4 2 2 + EAm. + (RMTE + RD) + (RTE) + (RCA + RMTEP) ]12 + zA,,.t, PMAFhf? + ]?MAPee .. re . P"MAftb + PMArxuLeyV,1itr + PMA,1tad#1,D,
" [ (0.50 + 1.50)2 + (0.50)2 + (0.63)2 + (0.50 + 0.50)2 + (0.50)2 +
(0.08 + 1.00)2 + (0.50)3 + (0.50 + 0.08)2 11/2 + (0.00) + (0.00) + (0.40) + (0.40) + (1.90) + (0.00) + (2.30) 7.77 t% Span [References 2.8 (WCAP Table 3-10c), 2.9.a and 2.151 As noted per Table 3-10A, the above CSA' computation includes: a 1.5% Span sensor I drift uncertainty (versus the 2.0% Span value originally assumed in References 2.8 and 2.9.a); and conservatively chosen Biases which reflect worst-case values. TS' " 25.0 % Level [Reference 2.13.a (UFAPPD, Table 2.2)] SAL' - 16.1 % Level [Reference 2.13.a (UFAPPD, Table 2.2)] W Note that Reference 2.4.d acknowledges that Low-Low RSG Level SAL was assumed for conservatism, since an SAL value is not credited in the Safety Analysis for an assumed loss of normal feedwater. TA' s { ( TS' - SAL' ) / 100 % level ) x 100 % Span f 8.9 % Span Margin
- TA' - CSA' , 1.13 % Span I
S' a ( (SD) + (SCA) ) - C (1.50) + (0.50) ) a 2.00 '% Span V (A')"12 + Biases 2
- ((SPE) 2 + (STE)P + (RTE) 2 )1 ' + rL + EA.,, + ?MAN.61 L+
PHAPre.r,. + PM&*.beco + PHA4piua + PHA*U,.t.D,
* ( (0.63)2 + (0.50)2 + (0.5)2 )1/2 + (0.00) + (0. 0) + (0.40) +
(0.40) + (1.90) + (0.00) + (2.30) - 5.95 '% Span I RI - T' is the lesser of: Ts.1' - RD + RCA) U ( (1.0) + (0.5) ) - 1.50 % Span IJ T21 TA' - S' - Z" U 8.90 - 2.00 - 5.95 0 0.95 % Span AV' - C TS' - I R'/100%Span ] x 100 % Level ) a 24.05 % Level Since the above-noted trip setPoint corresponds to a requirement for the Model A75 replacement steam generators [RSGu], the current Tech Spec values (associated with the Model D-4 SGs) are not directly comparable. The summary which follows (for current and post-PUR/SGR values) has been provided for completeness only:
CALCULATION NO. HNP-I/INST-1010 PAGE 55 REV. 3 TABLE 3-1OC (Cont'ld) STEAM GENERATOR WATER LEVEL, LOW Summary of CSA and Five-Column Tech Spec Terms Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 19.2 % Span 8.9 % Span Z Term 2.23 % Span 5.95 % Span Sensor Error (S) 2.97 % Span 2.0 % Span Trip Setpoint (TS) > 38.5 % level > 25.0 % level Allowable Value (AV) > 36.5 % level > 24.05 % Span
CALULArTION NO. ENP-I/INST-1010 PAGE 56 REV. 0 TABLE 3-11 STEAM/FEEDWATER FLOW MISMATCH Sunnnary of CSA and Five-Column Tech Spec Terms This trip function is based upon a high mismatch setpoint signal between steam flow and feedwater flow, coincident with the SO N-R Level Low setpoint. The steam flow input is density-compensated from the main steamline pressure channel. The current and post-PUR/SGR mismatch trip setpoints ETS and TS'I have been maintained at a 40% flow mismatch (i.e., original accident analyses scenario assum d a 100% steam flow and a 60% feedwater flow). This mismatch trip function is considered a backup to the SO N-R Level Low-Low trip function; as such, no credit is taken for this RTS trip function within current (and post-PUR/SGR) SPC Safety Analyses. The initial CP&L design input provided to Westinghouse per Reference 2.12.b [HW199-0381 assumed that existing steam and feedwater flow spans would be maintained (to preclude hardware replacements), and that renormalization of flow loops would be performed to correspond to the increased flows at 100% operation. Therefore, a re-duction for the original, nominal 120% flow range to an expected 116.55% flow range was assumed (given the 4.29 MPPR maximum PCWG 100% uprated flow condition, relative to the existing 5.0 MPPH max4mum range [PCWG Case 35 per Ref. 2.20.cl). Zn addition, a slightly lower 100% uprated flow of 4.24 WPPH (relative to the 5.0 NPPR maximum range [PCWG Case 30 per Ref. 2.10.cJ) has been identified, which would yield an expected 117.93% flow range. SFor com=arison to RSG only operation at current power conditions, computations at an expected 122.94% flow range can also be evaluated, based upon the current 100% operation at 4.067 XPPH (relative to the 5.0 MPPK maximum range [PCWG Case 1 per Ref. 2.10.0J). The use of this design assumption maximizes (or conservatively bounds) the mismatch trip channel uncertainty, independent of the flow range selected for final design implementation. Using the terminology within Reference 2.9.1 [cN-SSO-99-18, Rev. 1, Pages 23 and 24, the following adjusted conversion factors were computed for use herein: Feedwater Flow Conversion (to convert uncertainties from % DP xntr span to % flow span, Ref. 2.9.1 used 0.97)t CFF.tt.s.. - FMAX/(2x FFNOM) w 122.94/(2x&0) a 1.0245 Cr t 117.9*3 F=A/(2XFTNOM) w 117.93/(2x60) 0 0.9827 Steam Flow Conversion (to convert uncertainties from % DP xmtr span to % flow span; Ref. 2.9.1 used 0.58): CSFt 122.94% FHAX/(2xSPNOM) - 122.94/(2xI00) - 0.6147 CSFt 117.93%i " HAX/(2xSFNOM) - 117.93/(2x100) - 0.5896 An additional conservative input assumption for the steam pressure span to flow span conversion factor [CSP] was used by Westinghouse, by rounding off the 1.142 proportionality constant to 1.2, for all steam pressure transmitter and process rack uncertainties. This conversion process is consistent with the methodology originally used in Reference 2.3 [FCQL-3551, and per PUR/SGR project documentation within Table 3-24 of Reference 2.8 EWCAP-15249]. Using the following equations generally shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for ] jthis trip function.
CALCOLATION NO. ENP-X/INST-1010 PAGE 57 REV. 0 TABLE 3-11 (Cont'd) STEAM/FEEDWATER FLOW MISMATCH Summary of CSA and Five-Column Tech Spec Terms CSA' [ (SF_]pa)= + (+F pa)P + (Srrt*)3 + (SF-smte + S6Fd)2 + (Srspe)3 + (srFst&) + (SFrsra)2 + (SFrsca + F._smte)z + (S_.rmte + SFrd) 2 + (SFrca + SFrmte)2 + (Frsmte + FFsd)2 + (Flxpe)2 + (Fr? te)* + (CFrsra)* + (Fr_?ca + 77_smte)3 (FF~rmte + FFrrd)2 + (FF.rca + Fr_rmte)2 + (Bpsmts + 8P_sd)2 + (SP..te)2 + (SPsra)2 + (SP-sca + SP.umte}) + (SP rit. + SPBrd)2 + (SP-rca + SP._rmte)a 31/2 Using the above CSA" equation, reconciled channel Uncertainty Components have been determined in the following manner. This computation also considered the possibility of replacement of existing Barton 764 steam flow transmitters with Rosemount 1154DP5 series transmitters. This calculation utilizes the maximum uncertainty component of % Flow Span and transmitter model. Steam Fl >w Channels, Barton 764 RoDOMount 1154DP5
% DP % Flow Span % Flow Span %DP s low Span
% % Flow Span XaXiMnn Parameter span [122.94% Span? 1117.93% span] span t122.94% Span? [1M7.93% Span? Plow Span SFrpma 2.44 2.54 --- 2.44 2.54 2.54 SF.pea SFr__ ra 0.50 0.31 0.29 0.25 0.15 0.15 0.31 SFsca 0.50 0.31 0.29 0.50 0.31 0.29 0.31 Ssismte 0.54 0.33 0.32 0.54 0.33 0.32 0.33 SFrspe 0.50 0.31 0.29 0.30 0.18 0.18 0.31 SFste 0.50 0.31 0.29 0.95 0.59 0.56 0.59 SF_sd 0.77 1.25 0.77 0.74 1.25 0.77 0.74 SF_rca --- 0.50 0.50 --- 0.50 0.50 0.50 SFzrmte 0.20 0.20 0.20 0.20 0.20 SF_rte --- 0.50 0.50 0.50 0.50 0.50 SF_rd 1.00 1.00 1.00 1.00 1.00 Feedwater Flow Channels: Steam Pressure Channels:
% DP % Fo1w Span % Flow Span % Flow Span Parameter span [122.94% Span) 1117.93% Span] %Flow span Parameter % span [all Spansl FF..pna -rZ ------ ... SP..pina-.
rFpea ._0 0.41 0.42 0.42 rr_sra 0.25 0.26 0.25 0.26 SP._sra 0.50 0.60 rrsca 0.50 0.51 0.49 0.51 SP_?ca 0.50 0.60 Fr_smte 0.54 0.55 0.53 0.55 SP_sma o 0.54 0.65 WF spe 0.30 0.31 0.29 0.31 s _spe ...... rFste 1.10 1.13 1.08 1.13 SP-ste 0.50 0.60 rr_sd 1.25 1.28 1.23 1.28 SPsd 1.50 1.80 flrrca ___ 0.50 0.50 0.50 SP-rca 0.50 0.60 FF rmte 0.20 0.20 0.20 SPF_*to 0.20 0.24 FF_r t e . . .. .. SPrte ... ... FFrrd --- 1.00 1.00 1.*00 Sprd 1.00 1.20
CALCULATION NO. IHNP-Z/INST-1010 PACE 58 REV. 0 TABLE 3-12. (Cont"d) STEAM/FEEDWATER FLOW MISMATCH Summary of CSA and Five-Column Tech Spec Terms CSA' - [ (2.54)2+ (0.42)2 + (0.50)2 + (0.33 + 0.77)2 + (0.31)2 + (0.59)2 + (0.31)2+ (0.31 + 0.33)2 + (0.20 + 1.00)2 + (0.50 + 0.20)2 + (0.55 + 1.28)2 + (0.31)2 + (1.13)2 + (0.26)2 + (0.51 + 0.55)3 + (0.20 + 1.00)2 + (0.50
- 0.20)" + (0.65 + 1.80)2 + (0.60)2 +
(0.60)2 + (0.60 + 0.65)2 + (0.24 + 1.20)2 + (0.60
- 0.24)2 ]112 = 5.466 % Flow Span TS a 40.0 % Rated Flow [Reference 2.11 SAL' n N/A [References 2.3 and 2.13.a]
TA - 20.0 % Flow Span [Reference 2.13 Current Tech Spec TA was used, for evaluation of 5' & Z'. Margin - TA - CSA' 9 20.0 - 5.47 -- 14.53 % Flow Span St Barlew U ( (SF.sd) + (SF-sca)) U ( (0.77) + (0.31)) - 1.08 % Flow Span -w 1.1 % Flow Span S'rwrlow U {(FF..sd) + (FF-sca)) U ( (1.28) + (0.51) ) W 1.79 % Flow Span -- 1.8 % Flow Span
- S((SPsd) + (SPsca))
U ( (1.80) + (0.60) ) 2.4 % Flow Span Z - (A') 1 t 2 + Biases
- ( (pA) 2 + (PEA) 2 + (Total SPE) 2 + (Total )T)2+(RTE) 2 . 2 + EA +Bias 2 2
* ( (SFp=)n2 + (FFrpea) + ( [CSFspe) + (FFppe)2 ] 11 2 )2+
( [(Sp_ ute) 2 + (F?_sto) 2 + (Sp.._.sto) 2
]1/2 ) 2 (Srrte) 2
)1 1 2
÷7A+ias
, {(2.54).+ (0.42)2+ j(0.31)2+ (0.31)23 + [(0.59)2+ (1.13)2+ (0.60)23 + (0.5)2)112
+ (0) + (0) - (9.0552 )1/2 - 3.0092 , 3.01 % Flow Span The above-computed Z' term has been reduced from that shown in the current Tech Specs, owing to the elimination of the thermal nonrepeatability bias previously assumed for originally installed Barton 764 feedwater flow transmitters.
2 RO - (SFrd + SF_rca)2 + (F._rd* FF+_rca)2 + (SPrd + SP_rca) )112
- ((1.0 + 0.5)2 + (1.0 + 0.5)2 + (1.2 + 0.6)2)]L2
- { (2.25) + (2.25) + (3.24) )112 {( 7.74 )" 2 2.782 % Flow Span Using a 122.94% Span (versus the original plant design of 120% Span), which incor-porates steam/feedwater flow conversion values based upon the current 5.0 MPPH/4.067 MPPH maxi=um/100% flow ratio, a worst-case allowable value (designated by AV,') can be computed for SGR only operation. However, for PUR/SGR operation at the maximum 5.0 MPPH/4.24 MPPH flow ratio, PUR/SGR rescaling will result in a 117.93% Rated Flow span and a corresponding PUR/SGR allowable value AV2 1 .
AVL I a ( TS + I R'/100%Span ] x 122.94 % Rated Flow )
, 40.0 + 0.0278 x 122.94 a 40.0
- 3.417 - 43.417 % Rated Flow
CATLCLTION NO. RNP-XIXNST-1010 PAGE 59 REV. 0 TABLE 3-11 (Cont'd) STEAM/FEEDWATER FLOW MISMATCH Summary of CSA and Five-Column Tech Spec Terms AV2 ' - ( TS + [ R'/100%Span 3 x 117.93 % Rated Flow ) W 40.0 + 0.0278 x 117.93 - 40.0 + 3.278 - 43.278 % Rated Flow The above-computed AV' values are comparable to the current Tech Spec AV of 43.1% full steam flow at RTP; the current AV should be used owing to its slightly smaller value. The current Tech Spec TA - TA' should also be used, as specified above. The above-computed Z' and 9' values are applicable for PUR/SGR and/or SCR only operation, given the conservative conversion factors/uncertainty components eMloy-ed. A comparison of current and post-PUR/SGR values are summarized as follows: Tech Spec Term Current Tech Spec Value Post-PUR/SCR Value Total Allowance (TA) 20.0 % Span 20.0 % Span Z Term 3.41 % Span 3.01 % Span Sensor Error (S) Per current Note 6 Per new Note 6 (see below) Trip Setpoint (TS) < 40.0 % Steam Flow at RTP < 40.0 % Steam Flow at RTP Allowable Value (AV) < 43.1 % Steam Flow at RTP < 43.1 % Steam Flow at RTP Post-PUR/SCR Note 6: The sensor error (in % Span of Steam Flow) is: 1.1%for steam flow; 1.8% for feedwater flow; and 2.4% for steam pressure.
CALCULATION NO. HNP-I/INST-1010 PAGE 60 REV. 0 TABLE 3-12A CONTAINMENT PRESSURE - HIGH-1 & HIGH-2 Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. 2 CSA' - E (PMA) + (PEA) 2 + (SMTE + SD) 2 + (STE) 2 + (SPE) 2 + 2 2 (SCA + SMTE) + (MRA) 2 2
+ (RMTE + RD) + (RTE)2 + (RCA + RMTE) jl/2 a C (0.00)2 + (0.00)2 + (0.71 + 1.00)2 + (0.50)2 + (0.00)2 +
(0.50 + 0.71)2 + (0.50)2 + (0.50 + 1.00)2 + (0.50)2 + (0.50 + 0.50)2 11,2 2.89 -- 2.9 % Span [Reference 2.9.3 & Reference 2.8 (WCAP Table 3-12)] Note that above CSA' computation includes a 1.0% Span sensor drift uncertainty (ver-xus the 1.25% Span value assumed in References 2.8 and 2.9.j), based upon subsequent review of As-Found/As-Left drift data and for consistency with the "transmitter allowable drift [TAD]" value defined per current channel scaling calculations. TS M 3.0 psig [Reference 2.13.a (UFAPPD, Table 2.18)) SAL, - 5.0 psig [Reference 2.13.a (UFAPPD, Table 2.18)] TA' a C ( SAL' - TS ) / 55.0 psig Span ) x 100 % Span - 3.64 % Span margin m TA' - CSA' - 0.74 % Span S' m ( (SD) + (SCA)) ( (1.00) + (0.5) an 1.50 % Span Z' - (A')112 + EA -{ (PMA) 2
+ (PEA) 2
+ (SPE) 2
+ (STE) 2
+ (RTE) 2
)112 + EA
{ 03 + 02 + 02 + (0.50)2 + (0.50)2 )112 + 0.00 a 0.71 % Span RI - T' in the lesser of: T," a ( RD + RCA ) - { (1.0) + (0.5)) - 1.50 % Span T21 a TA' - S' - Z' m 3.64 - 1.50 - 0.71 a 1.43 % Span AV' a ( TS + C R'/100%Span ] x $5 psig be 3.79 psig The computed AV' is greater than the current Tech Spec AV of 3.6 psig. Therefore, AV, - AV - 3.6 psig will be retained for PtTR/SGR operation. A comparison of current and post-PUR/SCR values are suzmarized as followsz Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 2.7 % Span 3.64 % Span Z Term 0.71 9% Span 0.71 % Span Sensor Error (S) 1.5 % Span 1.5 % Span Trip Setpoint (TS) c 3.0 psig < 3.0 psig Allowable Value (AV) ' 3.6 psig < 3.6 psig
CALCULATION NO. HNP-II2NST-1010 PAGE 61 REV. 0 TABLE 3-12B CONTAINMENT PRESSURE - HIGH-3 Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA - [ (p1MA) 2 + (PEA) 2 + (S=TE + SD)2 + (STE) 2 + (SPE) 2 + 2 2 (SCA + SMTE) 2 + (SRA)a + (PMTE + RD)2 + (RTE) + (RCA + RMTE) ]112
- r (0.00)2 + (0.00)2 + (0.71 + 1.00)2 + (0.50)2 + (0.00)2 +
(0.50 + 0.71)2 + (0.50)2 + (0.50 + 1.00)2 + (0.50)3 + (0.50 + 0.50)2 31]2
- 2.89 -- 2.9 % Span (Reference 2.9.j & Reference 2.8 CWCAP Table 3-12)]
As per Table 3-12A, a 1.0% Span sensor drift uncertainty (versus the 1.25% Span value assumed in References 2.8 and 2.9.1) was used. TS - 10.0 psig [Reference 2.13.a (UFAPPD, Table 2.18)3 SAL'I 12.0 psig (Reference 2.13.a (UFAPPD, Table 2.18)] TA' - I ( SAL' - TS ) / 55.0 psig Span ) x 100 % Span = 3.64 % Span Margin n TA' - CSA' m 0.74 %'Span s, = ( (SD) + (SCA)) - ( (1.00) + (0.5) ) - 1.50 % Span 2 Z W (A') 11 2
+ ZA - ( (PMA) + (PEA) 2 + (SPE) 2 + (STE)' * (RTE) 2 )112 + ZA in
( 02 + 02 + 02 + (0.50)2 + (0.50)2 )1/2 + 0.00 0 0.71 % Span R, a T' is the lesser of: T X* I RD + RCA) - ( (1.0) + (0.5)) - 1.50 % Span T2. W TAP - S" - z" - 3.64 - 1.50 - 0.71 W 1.43 % Span AV' - ( TS + [ R'/100%Span I x 55 psig )
- 10.79 psig -- 10.8 psig The above-ccmputed AV' is comparable to that originally specified by FCQL-355 (with its round off to 11.0 psig). Given the slightly larger PUR/SGR SAL' value, the continued use of AV' - AV - 11.0 psig is justified. A comparison of current and post-PUR/SGR values are summarized as follows:
Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 3.6 % Span 3.64 % Span Z Term 0.71 % Span 0.71 % Span Sensor Error (S) 1.5 % Span 1.5 % Span Trip Setpoint (TS) < 10.0 psig C 10.0 psig Allowable Value (AV) < 11.0 psig < 11.0 psig
CALCULATION NO. HNP-I/INST-1010 PAGE 62 REV. 0 TABLE 3-13 PRESSURIZER PRESSURE - LOW, SAFETY INJECTION Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were co=puted for post-PUR/SGR Tech Spec terms for this trip function. CSA' - [ (PnA) 22 + (PEA) 2 + (SMTE + SD)3 + (STE) + (SPE)' 4 (SCA + SMT)2 + (SRA) + (RM=TE + RD) 2 + (RTE)3 + (RCA + p ) 12 + [ (0.00)2 + (0.00)2 + (0.71 + 1.00)2 + (1.44)2 + (0.00)2 + (0.50 + 0.71)2 + (0.25)2 + (0.5D + 1.00)2 + (0.50)2 4 (0.50 + 0.50)2 31,2 + (8.00) + (0.95) 12.11 % Span 2 [Reference 2.9.c & Reference 2.8 (WCAP Table 3-13)3 TS 1850 psig [Reference 2.13.a (UFAPPD, Table 2.18)) SAL - 1700 psig (Reference 2.13.a (UFAPPD, Table 2.18); Specifies a value of 1699.6 psig] TA ( C(TS - SAL ) / 800 psig Span ) X 100 % Span - 18.75 % Span Margin - TA - CSA'* 6.64 96 Span ýW) S' - ((SD) + (SCA)) - (1.0) + (0.5) - 1.50 % Span z - (A') 11 + EA I { (PMA) 2
+ (PEA) 2 + (SPE)3 + (STE)3 + (RTE)2) 1
'/ + EAT., + EAd
{ 02, 2 02 + 02 + (1.44)2 + (0.50)3 )112 + (8.00) + (0.95) - 10.472 % Span R- T" is the lesser of: T - ( RD + RCA ) = (1.0) + (0.5) , 1.50 % Span Tat TAP - ' -- Z' f 18.75 - 1.50 - 10.47 - 6.78 % Span AV' - ( TS - [ R'/100%Span I x 800 psiG } - 1838 psig The above-co*puted AV' in comparable to the original 1836 psig value specified by YCQL-355 (with current Tech Spec requirements based upon a T w 1.8 %Span and a CSA of 16.1 %Span); however, the computed value was selected for post-PUR/SGR opera-tion. A comparison of current and post-PUR/SGR values are summarized as follows: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 18.8 % Span 18.75 % Span Z Term 14.41 % Span 10.47 % Span Sensor Error (S) 1.5 % Span 1.5 9 Span Trip Setpoint (TS) : 1850 psiv > 1850 paig Allowable Value (AV) > 1836 psi; _ 1838 psia
CALCUL&TION NO. 1DTP-I/ZNST-1010 PAGE 63 REV. 0 TABLE 3-14 STEAMLINE DIFFERENTIAL PRESSURE - HIGH Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein (as modified as noted below), the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. This trip function must account for sensor and rack components from two different channels, for the physical comparison of the differential pressure between two steam lines; CSA, S, and R terms have been modified accordingly to represent these two [VA* and 'B'] channels. CSA' u [ (PMA,)3 + (PEA,)2 + (SHTEA + SDA)2 + (STE,)2 + (SPE,)2 + (SCAA + SMTEA) 2 + (SRAA)2 + (RMTEA + RDA) + (RCAA + RMTEA)2 + (RTE) 2 + (PMAD)2 + (PE.,) 2 + (SMTE, + SDV) 2 + (STE5)l + (SPE.)2 + (SCA, + SMTE,)2 + 2 (SRA,)2 + (3M, + p.aD,) + (jRCA, + RMTEz) ]112 + ZA
- [ (0.00)2 + (0.00)2 + (0.71 + 1.50)2 + (0.50)2 + (0.00)2 + (0.50 + 0.71)2 +
(0.50)2 + (0.50 + 1.00)2 + (0.50 + 0.50)2 + (0.50)2 + (0.00)3 + (0.00)2 + (0.71 + 1.50)2 + (0.50)2 + (0.00)2 + (0.50 + 0.71)2 + (0.50)2 + (0.50 + 1.00)2 + (0.50 + 0.50)2 ,112 + (0.00)
- 4.52 % Span (Reference 2.9.f a Reference 2.8 (WCAP Table 3-14)]
TS - 100 psi [Reference 2.13.a (UFAPPD, Table 2.18)] SAL - 165 psi (Reference 2.13.a (UFAPPD, Table 2.18)] TA - { ( SAL - TS ) / 1300 psig Span ) x 100 % Span - 5.00 % Span Margin i TA - CSA' W 0.48 % Span S', Z', and R' terms have been computed as follows, using the original FCQL-355 methodology, except for elimination of the Barton 763 thermal noarepeatabilIty bias (since the transmitters will not see excessive temperature exposures based upon their installation in the Reactor Auxiliary Building). Individual transmitters A & B were evaluated separately (by CA w SD, + SCA, - 1.0 + 0.5 - 1.5 %Span and, similarly, S, - SDe + SCA, - 1.5 %Span), consistent with the current Tech Spec total S tern of 3.0 %Span. Owing to the slightly larger sensor drift (of 1.5 %Span) assumed In PUR/SGR uncertainty analysis, a corresponding total 5' term would become 4.0 %Span. Alternately, a SRSS combination of total S error could be computed per the following: S' O C (SD, + SCA,) 2 + (SD, + SCA,) 23) - ( (1.5 + 0.5)3 + (1.5 + 0.5)3)1J C (4.0) + (4.0) )12 ( M 2.828 % Span -W 3.0 % Span Since this computation Justifies a value closer to the original Tech Spec S term, the continued use of S' - S a 3.0 % Span will apply; for operability evaluation purposes, each transmitter will be limited to a 1.5 %Span error (in keeping with the original Tech Spec values). Z' m (A')"1 2 + Biases - ((PMA) 2 + (PEA) 2 + (SPE) 2 + (Total STE) 2 + (RTE) 2 )1 2 +EA+Bias S ( (PMA)2+ (PEA) 2 + (SPE) 2 + ( E(STE,) 2 + (STE,) 2 *112
)2+ (RTE) 2) 1 2+EA+Bias
- { 02 + 02 + 02 + (E(0.5)2+ (0.5)2J112)2 + (0.50) )" + (0) + (0)
* (0.71)2 + (0.50)2)112 + (0) + (0) - 0.866 % Span
CALCULLTION NO. HNP-I/INST-1010 PAGE 64 REV. 0 TABLE 3-14 (Cont'd) STEAMLINE DIFFERENTIAL PRESSURE - HIGH Summary of CSA and Five-Column Tech Spec Terms It' .- { (RD. + RCAA)2 + (RD, + RCA,)2 )112 , (1.0 + 0.5)3 + (1.0 + 0.5)2 )1/2
, ((2.25) + (2.25) )1/2 a 2.121 % Span AV' - ( TS + E R'/100'Span 3 x 1300 psig ) - 127.56 psi The above-computed AV' is comparable to the current (127.4 psi) Tech Spec valuel therefore, AV' o AV a 127.4 psi will be conservatively retained for PUR/SGR operation. Z" has been reduced as noted above by eliminating the previously-assumed transmitter nonrepeatability bias.
A comparison of current and post-PUR/SGR values are su=marized as follows: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 5.0 % Span 5.0 % Span Z Term 1.47
- Span 0.87
- Span Sensor Error (5) 3.0
- Span 3.0 9 Span Trip Setpoint (TS) < 100 psi < 100 psi Allowable Value (AV) < 127.4 psi < 127.4 psi
CALCULATION NO. RNP-I/INST-1010 PAGE 65 REV. 0 TABLE 3-15 NEGATIVE STEAMLINE PRESSURE RATE - HIGH Sumary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-?URISGR Tech Spec terms for this trip function. All sensor-related uncertainty components have been set to zero, owing to the use of a rate (derivative) function to eliminate steady-state measurement errors. Therefore, this trip function must account only for rack coMponents to accomplish the rate of change measurement. 2 2 2 2 2 2 CSA' - [ (PMA) 4 (PEA) + (SMTE + SD) + (STE) + (SPE) + (SCA + SMTE) + (SRA)2 2 2 2
+ (RMTE + RD) + (RTE) + (RCA + RMTE) i1t2 + EA
- [02 + 02 + (0 + 0)2 + 02 + 02 + (0 + 0)2 + 02
+ (0.50 + 1.00)2 + (0.50)2 + (0.50 + 0.50)2 12: + 0.00 o 1.87 % Span [Reference 2.9.e & Reference 2.8 (WCAP Table 3-15)]
TS S 100 psi [Reference 2.2 and Reference 2.31 This function is not credited in the Safety Analysis [per Reference 2.13.a (UFAPPD, Table 2.18) and Reference 2.3 (FCQL-355)Js therefore, an SAL value has not been as-signed to this function. Since the current Tech Spec TA value of 2.3 % Span exists, STA' will also be set at 2.3 % Span. A margin of 0.43 % Span [2.30 - 1.871 exists between the current Tech Spec trip setpoint ITS] and total allowance [TA]. No sensor-related uncertainties are applicable, as noted above. S' - ( (SD) + (SCA) ) - { (0.0) + (0.0) ) - 0.00 % Span 2 2 Z' - (A')' + RA (( (PMA) 2
+ (pZA) + (SpE) 2 + (STE)2 + (RTZ) 2 1 12
) EA n ( 02 + 02 + 02 + 02 + (0.50)2 )112 + (0.0) - 0.50 % Span Re - T' is the lesser oft T," -W RD + RCA) - ( (1.0) + (0.5) ) 1.50 ' Span Ta"
- TA' - B' - Z" - 2.30 - 0.00 - 0.50 1.80 % Span AV' - ( TS + [ R'/100%Span I x 1300 psig ) - 119.5 psi The above-computed AV' is slightly less than that originally specified by FCQL-355 (with an actual T P 1.75 %Span), however, the computed value was selected for post-PUR/SGR operation. A comparison of current and post-PUR/SGR values are summarized as follows:
Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 2.3 % Span 2.3 % Span Z Term 0.5 % Span 0.5 % Span Sensor Error (S) 0.0 % Span 0.0 % Span Trip Setpoint (TS) < 100 psi < 100 psi Allowable Value (AV) < 122.8 psi < 119.5 psi
CALCULATION NO. HNP-I/IXNST-1010 PAGE 66 REV. 0 TABLE 3-16 TAVG - LOW, LOW (ESFAS P-12 INTERLOCK) Summary of CSA and Five-Column Tech Spec Terms Post-PUR/SGR values for the CSA" and AV' terms are discussed per the following. Uncertainty components applicable for post-PUR/SGR operation have been developed within Reference 2.9.m [CN-SSO-99-32, Rev. 03, and have been further summarized within Table 3-16 of Reference 2.8. CSA' - 3.2% of &T span [Ref. 2.9.m, Page 22 & Ref. 2.8 (Table 3-16)) This CSA" consists of: the SRSS of random uncertainties, associated with RCS N-R RTDs, R/E conversion within the process racks, and other process rack uncertainties; and the additive PMA biases associated with RCS Hot and Cold Leg streaming allowances, as well as the total R/Z non-linearity uncertainty for linear approximation of the RTD CR vs. T] curve. Owing to the operational flexibility required for startup and shutdown evolutions, the P-12 Permissive value has been retained within the same tolerance as that specified in current Tech Specs. Therefore, for completeness, post-PUR/SGR Tech Spec trip setpoint and allowable value can be summarized as follows: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) N/A N/A Z Term N/A N/A Sensor Error (S) N/A N/A Trip Setpoint (TS) > 553.0*F > 553.00F All.owable Value (AV) x 549.30F > 349.30r
CALCULATION NO. HNP-X/INST-1010 PAGE 67 REV. 0 TABLE 3-17 (Cont'd) STEAMLINE PRESSURE - LOW Suimmary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein, the following values were computed for post-PUR/SGR Tech Spec terms for this trip function. 2 2 2 2 2 CSA' - [ (PMA) + (PEA) + (SMTE + SD) + (STE)2 + (SPE) + (SCA + SMTE) + 2 2 2 (SRA) + (RHTE + RD)2 + (RTZ) + (RCA + RHTE) 11I2 + EA
- (0.00)2 + (0.00)2 + (0.71 + 1.50)2 + (0.50)2 + (0.00)2 + (0.50 + 0.71)2 +
(0.50)2 + (0.50 + 1.00)2 + (0.50)2 + (0.50 + 0.50)2 ]1l2 + (0.00)
- 3.21 %i Span [Reference 2.9.e & Reference 2.8 (WCAP Table 3-17))
TS - 601 psig [Reference 2.13.a (UAPPD, Table 2.18)] SAL' - 542.2 psig [Reference 2.9.e, Page 19 ("No MA for M&E Analysis")] Note that Reference 2.13.a (UFAPPD, Table 2.18) specifies original Reference 2.10.a
& 2.10.b uncertainty estimate of 370.9 psig (based upon the 370.5-psaig SAL specified in FCQL-355). The 370.9-psig value assum s an environmental allowance (if pressure transmitters are located in steam tunnel). These transmitters are located outside the HS Tunnel [in the Reactor Auxiliary Building Elev. 261'J, and will not be exposed to harsh environmental conditions for a Main Steam Line Break or Feedwater Line Break.
TA' - ( ( TS - SAL' ) / 1300 psig Span ) x 100 % Span a 4.52 % Span Margin - TA - CSA' - 1.31 % Span So - ((SD) + (SCA)) . ( (1.50) + (0.50) ) - 2.00 % Span Z' - (A') 1 1 + EA 2 2 2 2 112
- (pMA) + (PEA)* + (SPpZ) + (STE) * (Tz) ) +
,, 0 + 020 + + (0.50)2 + (0.50)2 )112 + (0.0) - 0.71 % Span R' n T' is the lesser of:
Tl I M ( RD + RCA) - ( (1.0) + (0.5) ) 1.50
- Span T2* W TAO - S' - Z' ,, 4.52 - 2.00 - 0.71 - 1.81 i Span AV' - I TS - E R'/100%Span I x 1300 psig ) - 581.5 psig The above-computed AV' is somewhat less than that originally specified by PCQL-355 (owing to T 1.8 %Span).
2 Given the above-noted elimination of the harsh environ-ment IEA] uncertainty, the above-computed values for CSA'. TA', and Z' are also correspondingly reduced. A comparison of current and post-PUR/SGR values are summarized as follows:
CALCULATION NO. MNP-I/INST-1010 PAGE 68 REV. 0 TABLE 3-17 (Cont'd) STEAMLINE PRESSURE - LOW Summary of CSA and Five-Column Tech Spec Terms Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 17.7 % Span 4.52 % Span Z Term 14.81 % Span 0.71 % Span Sensor Error (S) 1.5 % Span 2.0 % Span Trip Setpoint (TS) > 601 psig > 601 psig Allowable Value (AV) > 578.3 psig
- 581.5 psig
CALCULATION NO. WNP-I INST-1010 PAGE 69 REV. 3 TABLE 3-18 SG WATER LEVEL - HIGH-HIGH, BARTON 764 XMTRS Summary of CSA and Five-Column Tech Spec Terms Based upon the equations shown per Table 1-2 herein (as modified below), the follow-ing values were computed for post-PUR/SGR Tech Spec terms for this trip function. CSA' [ (SWTE + SD) 2 + (STE)P + (SPE) E 2 + (SCA + SMTE) 2 + (SRA) 2 + (RMTE + RD)' + (RTE) 2
+ (RCA + RMTE) 2 3112 + ZA,,.*,, + ZA=, +
PMAJt6,L. 9 Th.P + I:4*A*..r+ PMAso.b + PMArxlav.1.o1ty + ]PHL..rWCkKfl~tlPe 4" I
- [ (0.50 + 1.50)2 + (0.50)2 + (0.63)2 + (0.50 + 0.50)2 + (0.50)2 +
(0.08 + 1.00)2 + (0.50)2 + (0.50 + 0.08)2 3112 + (0.00) + (0.00) + (1.20) + (1.50) + (0.00) + (4.40) + (0.10) J
- 9.97 % Span [References 2.8 (WCAP Table 3-18a), 2.9.a and 2.15)
As noted per Table 3-10A, the above CSA' computation includes: a 1.5% Span sensor drift uncertainty (versus the 2.0% Span value originally assumed in References 2.8 and 2.9.a); and conservatively chosen Biases which reflect worst-case values. TS' " 78.0 % level [Reference 2.13.a (UFAPPD, Table 2.18)] SAL'
- 100.0 % level [Reference 2.13.a (UFAPPD, Table 2.18)]
TA' a ( (SAL' - TS' ) / 100 % level ) x 100 % Span s 22.0 %6 Span Margin u TA' - CSA' - 12.03 % Span I S' - C (SD) + (SCA)) - ( (1.50) + (0.50) ) - 2.00 % Span Z' - (A')"12 + Biases
. { (BPE) 2
+ (STE) 2 + (RTE) 2 1" 2 + E.AfL., + EAL.. + PMAftr. +
( Pq4rr***%e (0.63)2 +
+ PXA.*boe ..a (0.50)2 +
+ Pv1to4n61"Cvt (0.50)2)1'2 +
+
1 (0.00) PaLo-.rD.kIate
+ (0.00) + (1.20) +
I (1.50) + (0.00) + (4.40) + (0.10) = 8.15 % Span T' is the lesser of:
- (RD + RCA) U ( (1.0) + (0.5) ) o 1.50 % Span
- TA' - S' - Z' 22.00 - 2.00 - 8.15 - 11.85 % Span I AV' a ( TS' + C R'/100%Span I X 100 % Level ) a 79.5 % Level Since the above-noted trip setpoint corresponds to a requirement for the Model A75 replacement steam generators IRS0sI, the current Tech Spec values (associated with the Model D-4 SGs) are not directly comparable. The summary which follows (for current and post-PUR/SGR values) has been provided for completeness only:
CALCUL&TION NO. HNP-I/INST-1010 PAGE 70 REV. 3 TABLE 3-18 (Cont'cd) SG WATER LEVEL - HIGH-HIGH, BARTON 764 XMTRS Summary of CSA and Five-Column Tech Spec Terms Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 15.0 % Span 22.0 % Span Z Term 11.25 % Span 8.15 % Span Sensor Error (S) 2.97 % Span 2.0 % Span Trip Setpoint (TS) < 82.4 % level span < 78.0 % level span Allowable Value (AV) < 84.2 %6 level span < 79.5 % level span
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CALCULATXON NO. HNP-X/INST-1010 PAGE 73 REV. 0 TABLE 3-19 REACTOR COOLANT PUMP UNDERVOLTAGE - LOW Summary of CSA and Five-Column Tech Spec Terms Reference 2.4.1 [IMP Electrical Calculation E2-0010] documents the basis for current Tech Spec Trip Setpoint (TS) 'and Allowable Value (AV) of > 5148 volts and > 4920 volts, respectively. Reference 2.9.k [CN-SSO-99-17, Rev. 1] evaluated the uncertainties for this function, and confirmed that positive margin exists with the resultant CS?' of 10.29% of span. The Reference 2.9.k evaluation was based upon current MST-E0074 surveillance testing and acceptance criterion. (Note that this CSA' value was unchanged from the original CSA per Reference 2.3 [FCQL-355°.) Furthermore, it was noted that this trip function is not credited within current SPC accident safety analyses. Since no PURfSGR hardware changes are proposed for this function, no changes to the currentFfive-columnw Tech Spec values have been made herein. Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) 14.0 % Span 14.0 % Span Z Term 1.3% Span 1.3 % Span Sensor Error (S) 0.0 % Span 0.0 % Span Trip Setpoint (TS) > 5148 volts > 5148 volts Allowable Value (XV) > 4920 volts > 4920 volts
CALCULATION NO. MNP-I/INST-10l0 PAGE 74 REV. 0 TABLE 3-20 REACTOR COOLANT PUMP UNDERFREQUENCY - LOW Summary of CSA and Five-Column Tech Spec Terms Reference 2.4.J [INP Electrical Calculation E2-00111 documents the basis for current Tech Spec Trip Setpoint (TS) and Allowable Value (AV) of > 57.5 Hz and > 57.3 Hz, respectively. Reference 2.9.k [CN-SSO-99-17, Rev. 11 evaluated the uncertainties for this function, and confirmed that positive margin exists with the resultant CSA' of 1.81% of span. The Reference 2.9.k evaluation was based upon current MST-E0073 surveillance testing and acceptance criterion. Since no PUR/SGR hardware changes are proposed for this function, no changes to the current "five-columnN Tech Spec values have been made herein. Tech Spec Term Current Tech Spec Value Post-PtM/SGR Value Total Allowance (TA) 5.0 % Span 5.0 % Span Z Term 3.0 % Span 3.0 % Span Sensor Error (S) 0.0 % Span 0.0 % Span Trip Setpoint (TS) > 57.5 Hz > 57.5 Hz Allowable Value (AV) > 57.3 Hz > 57.3 Hz
CALCULILTXON NO. HNP-I/INST-1010 PAGE 75 REV. 0 TABLE 3-21 LOW FLUID OIL PRESSURE, TURBINE TRIP Summary of CSA and Five-Column Tech Spec Terms Refer to Reference 2.4.g (Calculation MOl-VINST-10553, Pages 5 through 9 for the basis for current Tech Spec Trip Setpoint (TS) and Allowable Value (AV) of > 1000 psig and >_ 950 psig, respectively. Since no PUR/SGR hardware changes are proposed for this function, no changes to these current Tech Spec have been made herein. Reference 2.4.g evaluated the acceptability of a 50-psig tolerance below the nominal setpoint as representative of the greater of either: a statistically calculated 44.78 psig [as-foundlas-left] drift allowance; or a 4 28 puig MST 'allowable range' (e.g., calibration accuracy setting). (Data Sheat (2 [of 41) from MST-X0260 [typical) reflects current calibration practices and as-found acceptance criterion.)
CAICULILTXON NO. HNP-ZIINST-1010 PAGE 76 REV. 2 TABLE 3-22 TURBINE THROTTLE VALVE CLOSURE, TURBINE TRIP Summary of CSA and Five-Column Tech Spec Terms Refer to Reference 2.4.f (Calculation IfP-I/ZNST-10543 for the basis for current Tech Spec Trip Setpoint (TS) and Allowable Value (AV) of > 1% open and > 1% open, respectively. Since no PIR/SGR hardware changes are proposed for this function, no changes to these current Tech Spec have been made herein. Reference 2.4.f evaluated the acceptability of the current MST iJplementation, in relation to the original Tech Spec TS and AV. MST-X0263 [typical] reflects current calibration practices and as-found acceptance criterion.) These practices/criterion can be summarized as follows, given the physical configuration and practicality of surveillance measurements:
- The '> 1% openw Tech Spec Trip Setpoint is actually calibrated as 2.37% open
((0.284-inches/12.00-inches)x1O0%I, owing to the 0.28-inch setpoint measurement over a total stroke of the valve (12.00-inch, 100% valve travel).
- This allows for variations between %As-Found' and 'As-Left' settings (histori-cally found to be within 0.164-inches (1.37%] of valve travel, which is equivalent to 0.45-inches of actuator travel).
" A 0.28 + 0.09-inch allowable range [i.e., from 0.19 to 0.37 inches] is maintained for the calibration/surveillance process. This allowable range utilizes a + 0.75% open 'As Left' calibration tolerance [C0.09 / 12.00 ) x 10D% ].
CALCULATION NO. ENP-I/INST-1010 PAGE 77 REV. 0 TABLE 3-23 RWST LEVEL - LOW-LOW Sunmary of CSA and Five-Column Tech Spec Terms Reference 2.4.h [Calculation ZQS-2) provides the RWST Low-Low Level setpoint requirement, to start switchover from RWST supply to the containment sump. This switchover setpoint is defined as 23.4% level by the current Tech Spec Trip Setpoint (TS). Reference 2.4.h also notes an historical 2.41% of span instrument error (as originally provided by Westinghouse Project Letter CQL8673, using the same methodology as contained in Reference 2.3 [FCQL-3551), which is enveloped by the 3.0% of span allowance provided by the current Tech Spec Allowable Value (AV) of 20.4% level. Reference 2.4.c [Calculation HNP-X/INST-1030] provides a computation of EOP indication accounting for the total of all channel uncertainty components (i.e., from the level transmitter through the process racks and MCB indicator). For consistency with other uncertainty computations performed for post-PUR/SOR operation, CSA' has been computed herein using the Table 1-2 equation/terms. This result is also reconciled in relation to existing plant documentation. LT-990 & LT-992 are Barton Model 752 transmitters, and LT-991 & LT-993 are Rosemount Model 1153DP transmitters; therefore two different sets of uncertainties have been shown for the installed transmitters, with a reference/explanation for values chosen herein: Uncertainty Uncertainty Uncertainty Parameter (w/Barton Xmtr) (w/Rosemount Xmtr) Reference(s) / Notes PHA 1.21 1.21 See Note I (below) PEA 0.00 0.00 Not Applicable to level measurement ERA 0.31 0.25 INST-1030, Sect. 5.lA.1 and 5.1B.1 SCA 0.50 0.50 INST-1030, Sect. 5.1A.10 & 5.1.B.10 SHTE 0.71 0.71 INST-1030, Sect. 5.1A.9 and 5.1.3.9; So* Note 2 (below) STE 1.44 1.89 INST-1030, Sect. 5.1A.3 and 5.1B.3 SPE 0.00 0 0.00 INST-1030, Sect. 5.1A.5 and 5.1B.5 SD 1.25 1.01 INST-1030, Sect. 5.2A.2 and 5.1B.2; See Note 3 (below) ZA 0.00 0.00 Not Applicable (INST-1030,Soct.4.5) SEISMIC 0.00 0.00 Not Applicable (INST-1030,Sect.4.13) RCA 0.50 0.50 Tyical value per Ref. 2.9.x CNs PME 0.50 0.50 Typical value per Ref. 2.9.x CNs RTE 0.50 0.50 INST-1030, 5.4.3 RD 1.00 1.00 INST-1030, 5.4.2 Note I: INST-1030, Section 5.5.1 states that: increasing density affects level with negative uncertainty (i.e., a resultant higher level), and decreasing density effects level
CALCULATION NO. MNP-I/INST-1010 PAGE 78 REV. 0 TABLE 3-23 (Cont'd) RWST LEVEL - LOW-LOW Sumnary of CSA and Five-Column Tech Spec Terms with positive uncertainty (i.e., a resultant lower level). zNST-1030 Positive and Negative Uncertainties of -1.21% and +0.34% were calculated. Consistent with the conservative assumption made within ZNST-1030, +1.21 was selected as a random uncertainty component for CSAI computation herein, since tRe assumed higher level will result In an additional measurement uncertainty with respect to the decreasing Low-Low level setpoint. This density effect is treated as a random uncertainty in INST-1030, because of the unknown direction of the change in temperature and/or concentration (and resultant density change). Note 2: Sensor )TZin and MTrout uncertainty components specified in INST-1030 are shown as a corresponding SRSS value. Note 3t Based upon comparison of "au-left- and subsequent has-found" XS= calibration data and the MS= allowable transmitter drift, this value has been reduced to a realistic value of 1.25% of span for the purposes of this CSA' computation (in lieu of that assumed by INST-1030, Section 5.1A.2). CSA'aarton - [(PMA)2 + (SMTE + SD) 2 + (STE)3 + (SCA + SMTE) 2 + (SRA)P + (RMT + RD) 2 + (RTE) 2 + (RCA + Prb=) 2
] 1' 2
- [ (1.21)2 + (0.71 + 1.25)2 + (1.44)2 + (0.50 + 0.71)2 +
(0.31)2 + (0.5 + 1.0)2 + (0.5)2 + (0.5 + 0.5)2]113
- 3.523 % of span 2 2 CSA'pRsenount * [(PMA) + (SMTE + SD) + (STE) + (SCA + SMTE) 2 +
(SRA) 2 + (pATE + RD) 2 + (RTE) 2 + (RCA + RMTE)) 2 312 [ (1.21)2 + (0.71 + 1.01)2 + (1.89)2 + (0.50 + 0.71)2 + (0.25)2 + (0.5 + 1.0)2 + (0.5)2 + (0.5 + 0.5)23]/2 3.606 % of span For subsequent discussions, the larger uncertainty of 3.606% span will be further evaluated for its effects to the subject ESPAS trip function. (3.606% span/100%) x (416.3 Inches WC [Xmtr Span, per 33NST-1030, Sect.4.9]) x (1-Ft/12-In) - 1.251-Pt of trip channel uncertainty, based upon CSA'. This is slightly larger than the 1.04-Ft measurement error assumed in Calculation EQS-2 (based upon the originally calculated Westinghouse Instrument error value of 2.41% Span). Since Calculation EQS-2 further calculated a 1.74-Ft (or equivalent 20,000 gallons) margin above the required switchover requirement with the current trip setpoint value, the small reduction [1.04 - 1.251 Ft w -0.211 Ft or -2.532 Inches] in this available margin will be negligible relative to the TS and AV. Since no PUR/SGR hardware changes are proposed for this function, no changes to the current Tech Spec TS and AV appear warranted, based upon the above dWiscussion.
CALC1=TION NO. ENP-IIINST-1010 PAGE 79 REV. 0 TABLE 3-24 6.9 KV E-BUS UNDERVOLTAGE - PRIMARY, LOOP Summary of CSA and Five-Column Tech Spec Terms Reference 2.4.1 [lIP Electrical Calculation 0054-JRGI documents the basis for current Tech Spec Trip Setpoint (TS) of > 4830 volts (with a < 1.0 second time delay) and an Allowable Value (AV) of > 4691 volts (with a < 1.5 second time delay). Furthermore, Reference 2.4.1 evaluated the acceptability for current calibration practices and as-found acceptance criterion as contained within MST-E0075. Since no PURISGR hardware changes are proposed for this function, no changes to these current Tech Spec have been made herein.
CALCULATION NO. MNP-I/INST-1010 PAGE 80 REV. 0 TABLE 3-25 6.9 KV E-BUS UNDERVOLTAGE - SECONDARY, LOOP Summary of CSA and Five-Column Tech Spec Terms Reference 2.4.k [HNP Electrical Calculation E2-0005.09] documents the basis for current Tech Spec Trip Setpoint (TS) of > 6420 volts (with a < 16.0 second time delay with Safety Injection, or with a < 54.0 second time delay without Safety Injection) and an Allowable Value (AV) of ' 6392 volts (with a < 18.0 second time delay with Safety Injection, or with a < 60.0 second time delay without Safety Injection). Furthermore, Reference 2.4.k evaluated the acceptability for current calibration practices and as-found acceptance criterion as contained within MST-E0045. Since no PUR/SGR hardware changes are proposed for this function, no changes to these current Tech Spec have been made herein.
CALCULATION NO. MIMP-I/INST-1010 PAGE 81 REV. 0 TABLE 3-26 RTS P-6 INTERLOCK Summary of CSA and Five-Column Tech Spec Terms Table 3-3 computations herein summarize uncertainties associated with the RTS trip function for the NIS Intermediate Range channels. In addition, an RTS P-6 Interlock is included as Tech Spec Table 2.2-1, Item 19.a. Its current (and post-PUR/SGR) Tech Spec Trip Setpoint CTSJ is > 1.0 x 10°" am. As noted in Table 3-3 herein, no PUR/SGR hardware changes are proposed for the Intermediate Range channels; channels will be scaled commensurate for the increased RTP (consistent with the detectors' increased output). The detector output span will continue to vary from I x 10-11 to I x 10-3 amp (corresponding to 0 to 120% RTP), with the following NIS IR rack transfer function: Voltageul.25[1 log1 0 (Input Current)+ I] or Input Current a 10 Setpoints are conservatively established (at relatively lower settings) during the start-up evolutions, commensurate with other known operating parameters. Furthermore, current maintenance surveillancelcalibration practices and acceptance criterion have proven acceptable to satisfy the current Tech Spec requirements. Therefore, the post-PURISGR Tech Spec Allowable Value [AV'] should remain unchanged from the original IMP Tech Spec requirements, at > 6.0 x 10'11 amp. This justification precludes the need for methodology, terminology, and values specified on Page 28 of Ref. 2.9.h. (Note that R' should approach the [current] AV, when drift is included with the rack calibration tolerance [RCA', as defined on Page 26 of Ref. 2.9.hl.) In conclusion, no changes to the current "five-column" Tech Spec term values (asso-ciated with this permissive function) have been made herein.
CALCULATION NO. MNP-I/XNST-1010 PAGE 82 REV. 0 TABLE 3-27 RTS P-7, P-10, AND P-13 XNTERLOCKS Summary of CSA and Five-Column Tech Spec Terms Conputations within Tables 3-1A, 3-1B, 3-2A, and 3-2B herein summarize various channel uncertainties associated with the RTS trip functions for the NIS Power Range channels. In addition, RTS Interlocks P-7, P-10, and P-13 (included as Tech Spec Table 2.2-1, Items 19.b(1), 19.b(2), 19.d, and 19.e) assure that plant start-up/ shutdown evolutions are controlled commensurate with permissible power level indica-tions (from either the NIS Power Range or the First Stage Turbine Impulse Chamber Pressure channels). These interlocks currently monitor plant operations around a nominal trip setpoint of 10% of RTPI a post-PUR/SGR Tech Spec Trip Setpoint ITS] based upon 10% RTP remains applicable. (These RTS Interlocks functionally perform either Blocks or Permissives associated with subsequent automatic protection/control actions. For example, the RTS P-7 Block (with inputs from either P-10 NIS or P-13 turbine impulse pressure) is based upon a < 10% RTP condition; the RTS P-10 Permissive (also generated from NIS channels) is based upon a > 10% RTP condition.) As noted in Table 3-2A through 3-2B for the NIS Power Range channels, no PUR/SGR hardware changes are proposed for these channels; channels will be scaled commensurate for the increased RTP (consistent with the detectors' increased output). Although not discussed within a specific computation within this calculation, Turbine Impulse Chamber Pressure channels will also not undergo PUR/SGR-related hardware changes (except for scaling completed for slightly higher uprated RSG and turbine impulse pressures)l turbine impulse chamber pressure P-13 input (to P-7) should be equivalent (for TS' and AV'] to the RTS input(s) received from NIS channels, since the subject RTS Interlocks for turbine impulse chamber pressure and NIS channels have the same functional requirements. NIS setpoints are conservatively established (at relatively lower settings) for protection/control purposes during the start-up evolutions, commensurate with other known operating parameters. Similarly, Turbine Impulse Chamber Pressure channels are inLtially scaled for conservatively expected power levels, and then re-normalized (if required) for that fuel cycle's operation. Plant power ascension procedural controls assure that manual operator actions are based on the most conservative indication of reactor power (e.g., AT, NIS, RCS flow, calorimetric) or turbine load (e.g., impulge chamber pressure, MWe output). Furthermore, current maintenance surveillance/calibration practices and acceptance criterion have proven acceptable to satisfy the current Tech Spec requirements. Note that R' was maintained per Table 3-1A herein, at 1.75% span [or 2.1% RTPJ. Therefore, the post-PUR/SGR Tech Spec Allowable Value [AV'] should remain unchanged from the original HNP Tech Spec requirements, at the nominal 10.0 + 2.1% of RTP (with its inequality based upon the specific [Block or Permissive] trip function requirement, in a direction commensurate with its corresponding TS). This justification precludes the need for methodology, terminology, and values specified on Pages 32-33 of Ref. 2.9.g (given that 'five-columnw AV [and AV'] include rack drift in addition to the rack calibration tolerance [RCA', as defined on Page 20 of Ref. 2.9.g].) LiIn conclusion, no changes to the current "five-column" Tech Spec term values (asso-ciated with this permissive function) have been made herein.
CALCULATION NO. ENP-I/INST-1010 PAGE 83 REV. 0 TABLE 3-28 RTS P-8 INTERLOCK Summary of CSA and Five-Column Tech Spec Terms The RTS Interlock P-8 (included as Tech Spec Table 2.2-1, Item 19.c) assures that plant start-up/shutdown evolutions are controlled cocaensurate with permissible power level indication from the NIS Power Range channels. This interlock currently monitors plant operations around a nominal trip setpoint [TS] of < 49% of RTP, with an Allowable Value [AV] of < 51.1% of RTP. Utilizing the same justifications as that provided within Table 3-27 herein (which support the maintenance of R' at 1.75% span [or 2.1% RTPJ), a post-PUR/SGR Tech Spec Trip Setpoint [TS'3 of < 49% RTP, and an Allowable Value [AV']
- 51.1% of RTP, remain applicable. This rationale precludes the need for methodology, terminology, and values specified on Page 31 of Ref. 2.9.g (given that %five-column- AV [and AV']
include rack drift in addition to the rack calibration tolerance [RCA', as defined on Page 20 of Ref. 2.9.g0.) In conclusion, no changes to the current *five-columnn Tech Spec term values (asso-ciated with this permissive function) have been made herein.
CALCULATION NO. HNP-IIINST-1010 PAGE 84 REV. 0 TABLE 3-29 ESFAS P-11 / Not P-1i INTERLOCK Summary of CSA and Five-Column Tech Spec Terms Tables 3-7A, 3-7D, and 3-13 herein summarize uncertainties associated with RTSIESFAS trip functions associated with Pressurizer Pressure channels. In addition, ESFAS P-1f and Not P-i1 Interlocks are included within Tech Spec Table 3.3-4, Item 10.a. The P-11 interlock currently monitors plant operations around a nominal trip setpoint ITS] of
- 2000 psig, with an Allowable Value [AV] of > 1986 psig. The Not P-Il interlock currently monitors plant operations around a nominal trip setpoint ITS] of < 2000 psig, with an Allowable Value [AV] of < 2014 psig.
Utilizing the same R' value of 2.50% of span (or 12.0 psig) determined from the above-noted Table 3-7A, 3-7B, and 3-13 sxumaries: a post-PUR/SGR Tech Spec Trip Setpoint [TS'] for the P-l1 Interlock of t 2000 psig, and an Allowable Value [AV,]
- 1988 psig, would apply; and a post-PURiSGR Tech Spec Trip Setpoint ITS'] for the Not P-i1 Interlock of < 2000 psig, and an Allowable Value [AV') < 2012 psig, would apply. This R" term includes rack drift in addition to the rack calibration tolerance, consistent with other Pressurizer Pressure covqputations documented herein.
Therefore, for completeness, post-PIM/SGR Tech Spec trip setpoint and allowable value can be smAarized as follows: P-i1 INTERLOCK: Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) N/A N/A Z Term N/A N/A Sensor Error (9) N/A N/A Trip Setpoint (TS) > 2000 psig > 2000 psig Allowable Value (AV) > 1986 psig
- 1988 psig NOT P-l1 INTERLOCK:
Tech Spec Term Current Tech Spec Value Post-PUR/SGR Value Total Allowance (TA) N/A N/A Z Term N/A N/A Sensor Error (S) N/A N/A Trip Setpoint (TS) < 2000 psig < 2000 psig Allowable Value (AV) c 2014 psig < 2012 psig
C C CT m
=
TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOIN1 TOTAL SENSOR ALLOWANCE ERROR C FUNCTIONAL UNIT (TA) z(S) TRIP SETPOTNT ALLOWABLE VALUE
-4
- 1. Manual Reactor Trip N.A. N.A. N.A. N.A. N.A.
- 2. Power Range. Neutron Flux
- a. High Setpoint 7.5 4.56 0 < 109% of RTP*" *111.1% of RTP'"
- b. Low Setpoint 8.3 4.56 0 5 25% of RTP*" *27.1% of RTP"'
- 3. Power Range. Neutron 0 r 5%of RTP'" with
- 6.3% of RIP'" with f% Flux. High Positive Rate a time constant a time constant Phb z 2 seconds z 2 seconds
- 4. Power Range. Neutron 0 *5% of RTP" with
- 6.3% of RTP" w{th Flux. High Negative Rate a time constant a time constant z 2 seconds ; 2 seconds 17.0
- 5. Intermediate Range. 8.41 0 : 25% of RTP" *30.9% of RTP" Neutron Flux 17.0
- 6. Source Range. Neutron 10.01 0 5 10' cps 5 1.4 x 10' cps Flux
- 7. Overtemperature AT
- Note 5 See Note 1 See Note 2
- 8. Overpower.AT See Note 3 See Note 4 0.
- 9. Pressurizer Pressure-Low 5.0 1.5 1960 psig
- 10. Pressurizer Pressure-High 7.5 ED~r.2385 psig 0
- 11. Pressurizer High Water Level- 8.0 E<r. 92% of instrument span
~0 High * . span span ". of instrument. (3s "RTP - RATED ThERMAL POWER
C C TAABB LLfZZ 44 - I Ca1c. No. MM-IIINST-1010 T-1010 3 TABLE-Z.2-1 (COnttnuedl Pagre 8766 LI, Cn REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOTf TA TOTAL ALLOWANCE FUNCTIONALUNIT (TA) - ALLOWABLE VALUE 90.5% of flloop Indicated o! full
- 2. Z 89.S% of flow indicated loop full
- 12. Reactor Coolant
.offarro'W t of narrow Steam Generator Water - range instrument span range Instrument span 13.
Level Low-Low Zn instf narrow ofnsrumentsn
- 14. Steam Generator Water'- ~t2~ range instrument span range instrument span Level - Low Coincident With 6 <flow 40% atof RTP" full steam Steam/Feedwater Flow 20.0 <sflow43. at 1%RTP ,
of .fullI steam Mismatch 14.0 1.3 0.0 2 5148 volts ,?-4920 volts
- 15. Undervoltage - Reactor Coolant Pumps 3.0 0.0 z 57.5 Hz z 57.3 Hz
- 16. Underfrequency - Reactor 5.0 Coolant PUMps
- 17. Turbine Trip N.A. N.A. 2 1000 psig Z 950 psig
- a. Low Fluid Oil Pressure N.A. ý 1%open N.A.* N.A. 2: %open
- 0. b. Turbine Throttle Valve N.A.
Closure I N.A. N.A. N.A. N.A.
- 18. Safety Injection Input 0
from ESF LA s'RTP - RATED-THERMAL POWER
IT C TAD£E 2.2-1 (tontInued) p t REACTOR TRIP SYSTEI4 tHSTRUMEHrATION TRIP SETPOJITS p SEHSOfl L0b TOAL ERR~OR
- 5 I.,
FUNCTIOHALUtI1T A 1JANCE iTA) ilL.._.TRIP SETPOiNT ALLO*WALE VALUE
- 19. Riactor Trip System
.3 interlocks
- a. Intermediate Range H.A. X.A. N.A. >1 x 10.10 ae
-4 _6 x 1O-11 amp
- Neutron Flux, P-6 V It ? b. tov Power Reactor Trips Block, P-7
- 1) P-10 Input N.A. N.A. N.A. <10% of RTP*X <12.1X of RTP**
- 2) P-t3 input N.A. N.A. N.A. <1Q0 RTP*e Turbine <12.1, RTP"* Turbine N Tapulse Pressure TiMpulse Presjure Equivalent SI Equivalent
- c. Power Range Neutron A.
ff. N.A. Nl.A. <49" of RTP** <51.1X of RTPA" Flux, P-8
- d. Power Range Neutron N.A. N.A. N.A %1O0of RTPA% 11.9 of RTP*.
Flux, P-1O
~1* up e. Turbine Impulse ChaEber H.A. N.A. N.A. <IO% RTP** Turbine <12.1% RTP** Turbine Pressure, P-13 Trpulse Pressure Topulse Pressure Equivalent Equivalent
- 20. Reactor Trip Breakers it.A. N.A HNA. N.A.
- 21. Automatic Trip and Interlock N.A. 11.A. H.,A. H.A.
Logi c I 2_2. Reactor Trip Bypass Breakers H.A. It.A. H.A. I.,' H.A. C. C, I
- I **RIP a PAIEO THERHAL POMER
'1
*1
(I (~. TABLE 2.2-1 (Continued) TABL-E-NOTAT TONSCae q M 1/NT 00 NOTE 1: OVERTEMPERATURE AT C AT (.I rS) I -T T] (P-P/)- fSAI) (1 + r2 S) 11+T 3S] (I+TS) L +
*T 8 s J
-4 Where: AT a Measured AT by RTD Instrumentation; 1 + T2S a Lead-lag compensator on measured AT; r?. T2 a Time constants utilized In lead-lag compensator for AT, r1 - r, s; I Lag compensator on measured AT; rT - Time constants utilized in the lag compensator for AT, T3 s; AT. a Indicated AT at RATED THERMAL POWER;
- K2 - O.0224/'F; I + r4S I + *rS The function generated bý the lead-lag compensator for T,, dynamic compensation; r4 , rs ,Time constants utilized in the lead-lag compensator for T,,,, r 4 - - 4 s;
a - TABLE 2.2-1 (Continued) TABLE NOTATIONS Ca1C. NO. 7MP-X/XNST-1010 70 Rev. NOTE 1: (Continued) TABLE 4-2. Page 89 T a Average temperature, 'F1 I a Lag compensator on measured T.,,; 1 + rTS
- Time constant utilized in the measured TV, lag compensator, r. - 0 s; T' C7 ' at RATED THERMAL PWE.
I K3 P/psig; 0.0012 7
- P Pressurizer pressure, psig; co PI = 2235 psig (Nominal RCS operating pressure); I S - Laplace transform operator, s't; and f, (AW) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(1) For q, - % between -21.6% and +12.0%, f, (61) - 0, where q, and q, ate percent RATED THERMAL I POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER In percent of RATED THERMAL POWER; (2) For each percent that the Mnitude of q - q6. exceeds -21.6%, the AT Trip Setpoint shall be automatically reduced b of Its value at RATED THERMAL POWER; and 4~9' '(175) (3) each percent automatically For that theMnitude reduced byE.E9I of %6 exceeds + 12.0%, the AT Trip Setpoint shall be
- q 0
y.%of its value at RATED THERMAL POWER. S. 0' NOTE 2 The channel's maximum Tr"N point shall not exceed its computed Trip Setpoint by more-than 1.4%s uof T span for AT inputg 2.n0% of AT span for Tavg inputt 0.4% of AT span for prsurizer pressure inputi and 0.7%~ of AT span for Al input. VressIt J
)
I
t() TABLE 2.2-1 (Continued) Cal. No. MP-X/INST-1O01 TABLE NOTATIONS pae 90 NOTE 3: OVERPOWER AT AT (1.* TrS)( (1(
)ATo 1*
- A)T" K - 5 (1+TS) 5
( -((sy)}
÷Ts) (121 6 S) *" "
- r T_*"
(1A) To_--_-- "
- f
'Wherel AT - As defined in Note 1,
.-0 I T As defined in Note 1, 1
- T2S
,.T 2 = As defined in Note 1,
- As defined in Note 1, s
I + V3 8 13 u As defined in Note 1, AT* a As defined in Note 1, K5 - 0.02/"F for increasing overage temperature and 0 for decreasing average temperature, SaThe function generated by the rate-lag compensator for Tayg dynamic I + T7 S compensation, T7 Time constants utilized in the rate-lag compensator for Tavg# T77 s
- B a1 1 - As defined in Note 1,
- V. 1 + T1 6S r0 16 As defined in llote I,
,C I-fl
= m TABLE 2.2-1 (Continued) CalL"- 110. 4-1 =P-X/INST-1010 TABLE NOTATIOtIS Page 91 I TABLE IA NOTE 3: (Continued) ? C K8 - O.002/°F for T > T" and K. - 0 for T -T".
-4 4
I-. T - - As defined in Note 1, T" -
- T,, at RATED THERMAL POWER I-...
S - As defined in Note 1. and f 2 (AI) - 0 for all Al. NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 1.4% of AT Spanl for AT input and 0.2%; of AT span for Tavg input., e
- 5 Te-Gensor-errs"' for tempvrtr
~]OE and- I~I9 p7Irsczui.c7
- ee Tw ;ccoc-fac steam-flaw is-0.9 for, feed-flow is 1.5. anA-#A---#--pressur-V 1-5 -, 1ý. 4-P n :;r.
ij V.I.J NOTE 5t The sensor error ist 1.3% of AT Span for AT/Tavg temperature measuremental and 1.6% of AT span for pressurizer pressure measurements. I
- a. NOTE 6: The sensor error (in % Span of Steam Flow) is: 1.1% for steam flowl 1.8%
for feedwater flowl and 2.4% for steam pressure.
/
K TABLE:_._1-2 Cale- 110- MO-VINST-1010 Rev. 0 page 92 TADLE 3.3-4 I __ czCý110 E"GINIIEREf SAFETY rEATURES ACTUATTOH SYSTEM IHSTRUMEKTATIOH TIRP SETPO a SEHSOR TOTAL ERROR FUNCTIOAL UNIT ALLOWlANCE (TA) TRIP SETPOIHT ALLOWABLE VALUE
'-4 'A, 1. Safety Injection (Reactor Trip, Feedvater Isolation, Control Room Isolation, Start Diesel Generators. Containment Ventilation Id Isolation, Phase A Containment I Isolation$ Start Auxiliary Feed-water System Motor-Drlven Pumps, Start Containment Fan Coolers.
Start Emergency Service Water Pups, Start Emergency Service Water Booster Pimps)
- a. Manual Initiation f.A. H.A. H..A. ".A. H.A.
'Ia 4
- b. Automatlc Actuation logIc H.A. ".A. H.A.. H.A. H.A.
and Actuation Relays
- c. Contalnment Pressure--111l- 0.71 -- 1 5 << 3.0 psig 3. %g gf_10.47) 1 3 qli!ý I. S
- 1850 psOO
- d. Pressurizer Presiure--Low
- e. Steam Line Pressure--tow MR
'(2 _-7JI P.
1ý2. -0
) 6601 psig
- 2. Containment Spray
- a. Manual Initiation N.A. H.A. H.A. II.A.
H.A. H.A. H.A. H.A. 11.A.
- b. Automatic Actuation togic and Actuation Relays
- c. Containment Pressure--Illgh-3 0.71 1.5 5 10.0 pslg 511.0 pstg I
KC IC I TABLE 3.3-4 (Contintied) ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMCHTATIOR TRIP SETPOINTS M 'A SENSOR TOTAL ERROR reNCTIONAL UNIT ALtOWANCE.(TA) Z (S) TRIP SETPOYHT ALLOWABLE VALUE
- 3. Contalnment Isolation 4A
- a. Phase 0Aw isolation
- 1) Hanual Initiation H.A. H.A. H.A. H.A. HWA.
- 2) Automatic Actuation Logic H.A. HeA. H.A. H.A. H.A.
and Actuation Relays
- 3) Safety Injection See Iten 1. above for all S4fety Injection Trip Setpoints and Allovable Values.
ob
- b. Phase "B" Isolattbn W I
- 1) "anual Containment N.A. N.A. H.A. ".A. H.A.
Spray Initiation
- 2) Automatic Actuation N.A.- HA. W.A. H.A. H.A.
Logic and Actuation Relays
- 3) Containment Pressure- See Item 2.c. above for Containment Pressure lllgho3 Trip Illlgh-3 Setpolnts and Allowable Values.
C. Containnt Ventilation Isolation -a
- 1) Manual Containment H.A. H.A. H.A. W.A.
- U:A.
Spray Initiation
- 12) Automatic Actuation H.A. W.A. W.A. H.A. H.A.
Logic and Actuation Relays
tC °( C TATE 3.3-4 (ContAnBed) P*CaILC.
- 4] "/ZS-00 x (H~NeYREFRFD SAFElY FEATURES AC'TVATTOH SYST(H INSTFRMEHTATTIfl TRIPLSI__ITPOINITSI SE1SOR z TOTAL ERROR FUNCTIONAL UNTr ALLOWAHCE TA) Z () TRIP SETPO TNT ALLOWAU.E VALUE
'-4 I
4-'
- 3. Containment Isolation (Continued)
I U
'-' 3) Safety Injection See Item 1. above for all Safety Injectfon Ti-iP Setpofnts and
- S..
I Allowable Values.
'-a I. 4) Containment Radioactivity I ~1k a) Area Honitors See Table 3-.3-6, Item Ua, for trio setpoint.
(both preentry and normal purges) b) Airborne Gaseous 1.h Radioactivity I Ia 0 (1) RCS Leak Detection See Table 3.3-6, Item Ibl, for trip setpotnt. (normal purge)
*1 c)
(2) Preentry PurGe Oetector Airborne Particulate See Table 3.3-6, Item 1W2, for trip setpotnt. .1 Radioactivity I. (1) RCS Leak Detection See Table 3.3-6, Item ICI. for trip setpoint. I (normal purge) (2) Preentry Purge Detector See Table 3.3-6, Item IC2, for trip setpolnt.
- 5) Hanual Phase M A" Isolation N.A. NI.A. N.A. H.A. N.A.
I
(C UTALE 3.3-4 (Contfnued) ENGIHEERED SAFETY FfATURES ACTUATIOtN SYSTEM INSTRUtJEHTAT!OI TRIP SETFOINTS V SENSOR TOTAL ERROR FUNCTIOHAL IUHIT ALLOWARCE (TA) Z (S) - TRIP SETPOIHT AtLOWABLt VALUE
- 4. Main Steam Line Isolatfon
- a. Hanual Initiationj3 H.A, H.A. N.A. ".A. N.A.
(PA
- b. Autoxatft Actuation tookf H.A. H.A. H.A. H.A. Nl.A.
and Actuation Relays
- c. Contaiument Pressure--ItIgh-2 0.71 1.5 03.0 psla 3. psUg CA I
- d. Steam Line Pressure--tow See Item I.e. above for Steam Mie Pressure--tow Trip Setpoints and f Allovable Values.
2.3 O.S 0 < 100 pi5r psi 1*
- e. Kegative ghSteam Line Pressure Rate--ilf
\6_193~)
S. Turbine Trip and Feedwater Isolation
- a. Auttmatle Actuation tookc H.A. H.A. f.A. H.A. H.A.
Actuation Relays I II
- 1
C- C TAMMEN04-2 H" 1/114ST Calc- NO- MM-WINST-1010 Rev. P age go 96 0 TARLE 3.3-4 (Continuved) ENGINEERED SAFETY-FEATRE ACUTO SYSTEM INSTRUMENTATION ITRIPETPO01rrS -4 SENSOR TOTAL ERROR C z .~. ALLOWA LE.VALUE -q FUNCTiONAL UTri ALtOnANCEd(TA) -4
- 5. Turbine Trip and Feedwater Isolation (Continued)
- b. Steam Generator Water ýnarrow of 0.4,range SY- of narrow range Instrument Level--High-High (P-14) instrument span.
tpan. C. c. Safety Injection See Item17. above for Safety Injection Trip Setpoints and Allowable Values. C', C. 6. Auxiliary Feedwater
- a. Handal Initiation N.A.
- b. Automatic Actuation Logic N.A. N.A.
and Actuation Relays Yof narrow
- c. Steam Generator Water ~ narrow range range instrument Level--Low-Low span.
Instrument span. Safety Injection Start See Item 1. abovoqor all Safety Injection Trip Setpoints and
- d. Al1owable Values: '.
Motor-Driven Pumps Loss-of-OffsIte Power See Item 9. bolowIfor all Loss-of-Offsite Trip Setpoint and
- e. Allowable Values.
rY Start Motor-Oriven Pumpk and a Turbine-Driven Pump
- f. Trip of All Main Feedwater N.A. N.A. N.A. N.A.
Pumps Start Motor-Driven Pumps
(C ( el. 0on-/~s-oo - P '~ea nP. TABLE 3.3-4 (Cont(nued) PIGIER(O SAFETY FEATURES ACTUATIOI SYSTEM IHSTRUtEHTATO TRIP SETPOrNTS SENSOR TOTAL ERROR vzMcrtfo'A "mir ALLOVANCE (TA) -_S) TRIP SETPOINT ALLOIJAOLE VALUE
- 6. Auxiliary Feedvater (Continued)
(. Steam I.ne Differential 5.0 a .0 < lOOpsM < 127.4 psi Pressure-IIlgh Coincident With See Item 4. above for Main Steam Line Isolation Trip Setpolnts Main Steam Line Isolation and llowable Values. 4-A (Causet AFI Isolation)
- 7. Safety Injection Switchover to Containment Sump
- a. Automatic Actuation looic.
H i.A. It.A. H.A. l. A. H.A. and Actuation Relays LA
- b. RWST Level--Low-oy HA. N.A. H.A. > 23.4% ) 20.4% I Coincident With See Item 1. above for all Safety Injection Trip Setpotnts and Safety Injection Allowable Values.
- 8. Containuent Spray Switchover to Containment Sump
- a. Automatic Actuation Logic N.A. NI.A. H.A. H.A. ff.A.
and Actuation Relays
- b. RWST--Lov-tov See Item 7.b. above (or all RWST--tov-Lov Trip SetpoInts in3 Allowable Values.
Coincident With See Item 2. above for all Containment Spray Trip Setpoint$. Containment Spray and Allowable Values. 0
.1l
(C TABLE 4-2 4-2 ABLE ff ftlc.no. MM-X/1f;ST-1O1O En ST_1010 Rev. ev 00 P age'a 98 TABLE 3.3-4 (Continued) go: z Ua ENCINEERE)D SAFETY FEATURES ACTUATION SYSTEM tNSTRIUKENTATION TRIP SETPOINTS TOTAL SENSOR ERROR I ALLOVANCE (TA) TRIP SETFPOIT ALLOVABLE VALUE FUNCTIONAL UNIT
.4 U-
- 9. Loas-of-OffeIte Power K.A. HIA. N.A. > 4830 volts > 4692 volts uwth
- a. 6.9 kV Emergency Bus idth a < 1.0 a time delay Undervoltage-Primary second rime
- 1.5 seconds delay.
N.A. N4A. HNA. > 6420 volts
- 6392 volts
- b. 6.9 kV Emergency Bus ;'th a < 16 ;ith a time Undervoltage- second lime delay 1 18 seconds Secondary delay (with (with Safety
'-I Safety Injection)*
8-Injection).
> 6420 volts > 6392 volts
*Ith a < 54.0 '[th a < 60 second Time second time delay (with- delay (with-out Safety out Safety Injection). Injection).
- 10. Engineered Safety Features ActuAtion System Interlocks 1908
- a. Pressurizer Pressure# H#A. N.A* > 2000 psig> psig H.A0
-P-ll W.A. H.A, N.A. Z 2000 psi Z Paig got P-1I rY 0
- b. Low-Lov T avg, P-12 HaA, H9A9 > 5536F 2012> 549.3?*
I U
(C TABLE 3.3-4 (Cont nued, I **)r.4?. f4 22 D
£1N;INEERED SXfETY V'EATURES ACTUATIONI SYSTEH4 INSTR*UXEfTATION TRItP SETPO!NTS 4
.4. SENSOR-TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA) (S RIP SETPOINT 7J~ ALLOWABLE VALUE fA j0. Engineered Safety Features Actuation System Interlocks (Continued)
-4 H.A. tf.A. N.A. ".A.
o I-.
- c. Reactor Trip, P-4 H.A.
- d. Steam Generator Water Level, See Item 5.b obove for all Steam Generator Water Level Trip Setpolnts I
P-14 1 and Allowable Values. U~
*1 Id Idm
%I I. I
- 1 I
TABLE 3.3-4 (Continued) ThPLE WOTATIONS
- Time constants utilized in the lead-lag controller for Steam Line Pressure-Lo,; are i. 2 50 seconds and T, : 5 seconds.
CHANNEL CALIBRATION shall ensure.that these timeI constants are values. I adjusted to these The time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate--High is k So seconds. CHANNEL CALIBRATION shall ensure that this time constant is adjusted to this value. u The indicated values are the effective, cumulative, rate-compensatid pressure drops as seen by the comparator. SHEARON HARRIS - UNIT 1 3/4 3-36 Amendment No. 89
C C TABLE 4-3 CALCULATItO NO. l12w-rIZNST-1010 SUlM7*tAY OF RTS/ZSrAS *F1r-COLV*m TzRM- PACE 101 FOR POST-PUR/SOR OPEfRTION R*V. 3 Table 2.2-1 Current flTve-Col,- Tech fspa Terms Prot-P*RSOR -rIVe-Co1--- Tech fpea Trms INS?- Total leneca "ate Sasser 1010 Allowance a Irror Trip 8otpolat Allowable value Allowancoe 3 Err Trip letpolut allowable Value Ite Functio*al it%" Table ITA) I.r. (a) ("I (fy) (TA) Term (3) (IV) a FI - -r - - - -- - 2.a Power Rano*. Ntro Flux - -1A 7.5 4.S0 0.0 S 101.0% at 1of S 111.1% of I79 B1gb Setpoint 7.1 4.15 0.0 1 109.0n of RTY 1 111.1% of M1? 2.b 70 ae Neutron Flux - 3-12 0.3 4.50 0.0 S M%Of IT# 1 27.1% ot STY, 6. Low Sotpoint 4.56 0.0 : 2t% of RTY 27.1% of It? 1S5 of rT S 4£.3% of RT *5% er IT? S 9.3% of ft2 Power Raneng, Neutron Flux - 23- 1.6 0,$ 0,0 with a with a 19*%pouitive Rato t,1 0.62 0.0 with a with a time constant time co*stant . 1time c .matentti4e 0osta"t of* 1 secoads of a 2 secede of 2 a ecd*ne of 1 2 secoade S 5%of3 TF 6.3%oflt £ S1% ofitA £61.3% of MT? 4 Power Mangre, woutron Flux.2? 1.6 0.1 0.p with a "t wim~tset '.a08 . witlo a Egig Negative FAte with 0 Lossn comanst tiecoa~tn .1. tin* , -atest tine eConstantI of X2 secot0* tf2 secoods of zl secands of X 2sc0"1a n teMrsodist Ran". 3-3 17.0 h.41 0.0 253%of ITP $ 30.9% of 17 17.0 0.41 0.0 S 25% of 17 i 36.9 of Neutron Flux 6 Source Range, Neutron Flux 3-4 17.0 10.01 9.0 S t10 cps t 1.4 a 10' cps 17.0 10.01 0.0 A 10' cps £ 1.4 3 10' evP 7 Overtswreture 6T 3-5 1.7 6.02 eote S Note I Mete 2 M.0 7.31 see not* 5 See Mote I 8ae Note 2 S Overpower T 3°g 4.7 1.30 1.9 note 3 Mote 4 4.0 .2.32 1.3 Se"note 3 e" bote 4" Preasuriver Pressure - Low, Y-?t f.q :.I 1.. i 1900 pelf 1 1946 pale 1.0 i.S2 1.1 a 1960 palo 2 I943 petgo Reactor Trip 10 IProssurtser Pressure - igh* 0 eacttr Trip g 3.7 7.1 5.01 0.o A 2361 pplff 2390 vote .5 1.. 1.1 A 2361 vlet S 2397 pelf Pressuriser water Level - 11 Rio% 2.6 6.0 2.21 1.1 1 92% ofspas Insruen lasrI1 9].6 9.7 of spas S.0 1.t3 175 19%o: of 1 91.1% 3Sf of etrnmeat span ltriment apia lnstrimnt span lnatrueet @pas 1, 99.5% of a 69.5% of a to.*% ot so.5% o0 12 Reactor Coolant Flow - Lwo 3-9 2.9 1.96 0.6 loow full loop full 4.56. 1.41 0.6 loop full loop full lndlcote4 flow in4icated flow indicated flow Isdiceted f*ow Sg water Leval, LoT-Low 28.$%otf )9.51% of I 12 (FW Liao pro&1%) 2 .0 . 25 off 1 31.5% of 3-1A 19.2 11.06 2.27 narrow range narrow ran"g 17.05. 2.0 LIntrument span Instrument span narrow rane instrument narrow range rsp Lnstrummat so" 80 Water L2vel, Lo--Lw 30.5% of a 3f.3% of 1 1 25% of 1 123.5%of SW L103 13.2 1.0 2.97 narrow range narrow range 25A (Laosat ofMorsel 7W) 17.41 2.0 narrow rang. narro range Iaatrubat span instrumaen span Inlstrumet span instrument span
C C () TABLE 4-3 CAWM~A??Olf NO. MrP4/ZNST-1010 SM"MRY OF RT$/ESAS FIVZ.COW)o TRMS PAGE 102 FOR POST-PUR/SGR OP!3tATIO? REV. 3 Table 2.2-1 Current "Five-Coluun' Tech SVeo Tms- post-FrnISGR. -tv*-Coluseng Tech Dp.c Terms I"ST- Total ssge*r Total sensor 1ol0 AlloswC* S Ixr" TWiP 8etpolat Alloweblo Vlue Allowance s irte"0 Item Trip Setpolat lloaIblosvalue iactioual Itm Table ITA) 'srm (31 IT7) (LW) (TL3 term (U) ITS) (Av) k 31. of . 3C." Of I S tem X 2S% at x 24.05% of 1atee Iearatowr 2-I0C 19.2 2.2) 2M.7 waow tease narrow range k. .9 Dow .0" na"ow rta" narrow ran"e atro t span Instrment span laatrm t spen Lsatrmats
-pan2 14 1toa/Foedletet lIe t40% of Flowof of £40%of 1 43.1% of 3-1. 20.0 3.41 note 6 full stem flow full steaM flow 20.0 .3.01 See itsnAtch at AT? fote 6 full steam flow full steam flow at 1T? at 3TV at RTP is Reactor Coolant PU*V 3-19 14.0 1.$ 0.0 1 5140 volts a 490 volts 14.0 1.3 0.0 k 5146 volts x 4920 volts neorwaltago -
16 *sector e V~orfraouenc lqant y Pum
¢ 3-20 1.0 3.0 0.0 57.1 3 Us a $7.3 Us $.0 3.0 0.0
- 574. 3s z 57.2 Us M7a w Fluld oli ?rse .*re, 3-21 WiL via via. 1 1000 Pail Turbine trip 150 peil 9 NI. via vIL *: 1000 pelf kI 90 peIl I7,b Turbine Throttle Valve 3-22 via WIA via, 1 l open Closure, Turbine Trip a 1% open via via 311. 1 % Ope*n 1 1% men M&.e P-4. Zntervdiate Range 3-26 Neutron Flux vIl VIA via. Ix x to's" a 6 x IoU e VIA VA1.I Ix $0-L awA 9 x l0o" o-P-7. Low, Power 19.b(l) Reactor Trip $lock 3-27 Nth VI& 3/1 j 10% Of RTP 1 12.1% of ATP 311 Nth 1L0/ 1 10% of 1? 1 12.1% of ITT (from 1-10 Input)
V-7, Low Pow I 10% of ITT
- 12.1% of MTP 1 10% of ITy 1 12.1% o5 *TV 19.b(Z) Reactor Trip loack 3-37 WA1 via 011. turbine 1Ivis Turbim 2l Mlke VIiA flia Tu eeau. uressure (free P-13 Input) Pressure "6eS iftesure tpeooere touivelent Kuivalant qnivalat qivaleut 19.0 -tv- Power Rang.ie 3-2 3/1 WA Nth I 4n% of RTP 1 51.1% of DiP Neutron Flux *I/& via. 3.ia $ 4 % of RYP A 11.1% of ITV 19.d F-100 Power Range 3-27 3/1 Ufa& f/a1 Weutron Flux a 10% of RIp
- 7.t%of UT? 3/1. 3/1. 311
- v. 10% of RTP & 7.V% of RTP
- 20 of RIP A 12.1% of ATP t.r,1 ofT? of It,* :-13, Turbine Immlee 3-27 VIA, N/A VIA TurbiDe M4ee t9urbine *InIless "I/ iee Trbflea Trbine Imiuls, Chamber Pressure 7esoure PresouIe pressure Pres equivalent Xquivaleat rquivalent gquiyalat Noties sea Tech Epea mark-up (:31r.1010, Table 4-1)
C C () TABLE 4-3 CALCMLATION NO. !NP-!/ZNST-10lO
SUMMARY
OF XTS/ESFAS oFrVtoLwm3e TrMS PAGE 103 FOR POST-WV'SGR OPERATION MeV 3 Table 3.3-4 Curreot -F7ve-Columna Tech ftpe Terms Post.WURIBSR OVIv-Coluan Tech Speo Terms 21"S- Total lessor Total lseor 1010 )l1@easo I error Trip IstpoLst Allewabloe alue Mlloawe 3 twrer %ton Trip selpolat Allorabl* Value iPunctlal Item Table (T1) rm is) (O) (Ly) ITS) ferm (IMI)
) (AV)
Cotimn -P-e-s-re - -
- l. Vontawihent Preaslr 11gb-i - 3-12A 1.7 0.71 1.5 1 3.0 pelf I 3. pll 3.4 0.71 1.5 S 3.0 peilf 3. pel C h,igh-2 Coostale et Preslure - 3-121 2.7 t.79 1.5 ___________________
1 3.0 Peli A 3.6 pellf E4 0.71 1.5 £ 3.1 psio 1 3.6 peil
- 2. 2. Contai3 igh-3 ) ut Prta5WZ* - 3.123 3.6 0.71 1.1 1 10.0 pelt 1 11.0 Vollt ,4 0.71 1.5 £ 10.0 pell
_ _ _
- 0' _ -
£ 11.0 pvlt a - - ++ *" -ld11--
- 1. v resuret Pressure &owe 3-13 10.1 14.41 1.5 k 1150 pill A 1336 psil 14 safety injection 1.15 10..47 1.5 1 1050 pesl I 1033 pavl 6.g 3tealtno Pressure - DIfsreutial 3.14 5.0 1.47 3.0 A 100 psi Slab S 127.4 pot 5.0 0.41 1.0 1 100 psi 1 123.4 pot 4.* Ha ti-e stvamLo Pressure 3-15 2.3 0.50 0.0 S 100 psi 1 122.0 pat 2.1 0.5 0.0 £ 100 ptVi 113.5 psa.
Kato - HighI 1.0 Stesmnlno Pressure - 1ow 3-17 17.7 Me.t1 1.5 . 101 p.i, k $70.1 poll 4.11 0.71_ 2.0 x 601 pslf k 301.5 pelf. Water L4"1 - 1 3llb*NlVh,
!I I2.4% of A l4.2% of
- 71.0% el 7i.5% ot.
5.b Bartor 7614 grs 3-11 15.0 11.25 2.01 marrow range warrow rosmw !1.04 .1 - 2.0 narrw rwase " aarrow can" 1rot6matri t op" ilstrumeat ap " ". imastvmet epa at*a*mmt span 1 31.1%01 A11,1% SI o 25.0%of
- 23.1% of 4., so water Leltel Low.Low 3-10A 1.2 14.06 3.17 "mSt raum" nsarew r*a" 21.1 11.4% 2. marrow reame naivm ran lastrumat ope nStr~mont go" Ltramo at w mLstrmta at8x 7.b xWT tevel . Low 3-23 VIA IlL VIA 1 23.,d a 10.4% VIA via NIa
- 21.4% a 20.4%
9.8 6,9 TV 2-su voervoltag. -
- 4330 Volta k 4002 volts x 4330 volts a 4652 wolts P6.0tlr 3-24 Nth oNt VIA vit% a 1 3.0 wit h tNuw N/1 NN/
LOOP seoo7d time delay A 1.5 kl wiath a t $.0 litha time
@*good tie dolor S 1.3 dotly mscoams delay soamea-9.b -a 4*30 Volts 't 6393 volts -a 4620 volts a 3932 voltvt
- 6. IV K-buy Undorvoltage - 3-25 vIa NIl V/A with a I 16 with a time 10/4 VIA 3/1 with a I 1 with a time Secondary. LOop seooem time dolos 11 60404ad tine dolay 1 18 delay (with vagoads (with doloy (with s*coeds (with Staety Safety lefety safety xsjectioni) ?ec-teles) xIaectlos) zTlection)
- 4420 volts x 6392 volts
- 6430 volts 1 6302 volts vito ha Al4.0 with a S with Oll4.0 with a i0 socund time $scemd time secod time seemed time doloy (without dolay (without delay (without delay (without safety safety safety safety Itiectiom) Taloction) _____lajectiom) ynlectioa)
- 10. P-211, Pressurixer Pressure 3-23 ia. VIA WiLt a 2000 pill a 1t04 pvil UIf l/A VIA Y. 3000 pill x 1411 poll 10.0 MT P-l1, PrfIeuriaIr Pressure 3-25 Ia VIA NIl t 2000 psti 1 2014 pel viL NtL I/a £2000 pill . 2012 psil 1O.b P312, Low-L*w Taog 3-16 XIA V/A NIA 2 552.0 *r A 14,3. *" V/A VIA */A x 551.0 "? 1 14f.3 '*
CALCULkTION NO. PAGP-EINST-1010 3IEV. 0 , PAGE AI-1 ATTACHMENT 2 Sheet 1 of 2 w Record of Lead Review Design- Calculation HNP-lIINST.1O1Q Revision 0 The signature below of the Lead Reviewer records that:
- the review indicated below has been performed by the Lead Reviewer;,
- appropriate reviews were performed and errors/deficiencies (for all reviews performed) have been resolved and these records are Included In the design package;
- the review was performed In accordance with EGR.NGGC-0003.
Design Verification Review D- Engineering Review 0] Owner's Review 0 Design Review O Alternate Calculation O Ouali'cation Testing [] Special Engineering Review E[ YES Z N/A Other Records are attached. Clyde R. Fletcher I&C 8/31/00 Lead Reviewer (print/sign) Discipline Dat Item No. Deficiency Resolution
- 1) Calculation Title should reflect current and Modified Calculation Title as suggested.
uprated power with SG Replacement.
- 2) Reo. 2.9.a should read 1H/99-06T. Ref. 2.4.1 Corrected typos as suggested.
should read "0054-JRG*.
- 3) Add reference to COL-98-052 [Calc Note Added [Reference 2.10.h] as suggested.
OPES(98)-025].
- 4) Section 4.0. 1" para.: Delete reference to "2- Deleted text as suggested.
column' Tech Spec terms comparison.
- 5) Table 1-1: Add RCSA term, and delete SRA Corrected as suggested.
term for FCQL-355 'A' &'Z definitions.
- 6) Table 2-3. Tech Spec Items 5b & 1Ob: Corrected as suggested.
Trip Setpoint should read _<(vs. ">").
- 7) Table 3-0: Add cross-reference to Westing- Added Table Column W Calc or Other HNP Caic house CNs or CP&L calculations. Ref(s)", as suggested.
- 8) Table 3-8: SPE term in CSA' should be 0.5; Corrected equations and results, as suggested.
Resultant CSA', Margin, Z', &T2' should be 5.26,2.75,3.416, &2.83, respectively. S9) Table 3-9: 0.13 Calorimetric Bias was specified InWCAP-15249. Table 3-21 as a PMA. CN-SSO-99-33 [Ref. 2.9.nJ, WCAP-12340 [Rev.1,
&INST-101 I confirms Bias treatment.
CALCULATION NO. HNP-I/INST-1010 REV. 0 , PAGE AI-2 A1TACHMENT 2 Sheet 2 of 2 Record of Lead Review Design CQacudation HNP-1/INST-1010 Revision Q_ I Item No. Deficiency Resolution
- 10) Tables 3-1 OA: Add basis for excluding Cable Added explanation InTable 3-1 0A, as suggested.
IRdegradation bias. Need for this bias not required for Table 3-1OB.
- 11) Tables 3-1 OA, 10B, 100, 18A, & 188: Reduce SD reduced to 1.5% span for all Tables. Justifica-Sensor Drift to a more realistic (but conserva- tion added to use historical drift data as basis for tive) value, reduction.
- 12) Tables 3-1 OA &3-10B: Confirm applicability of Applicability of Table 3-1 OA TA' and Z values within
[Table 3-1DB] LONF results for terms TA', Z, & Table 3-1OB are consistent with the current licens-S'as bounding for [Table 3-10A] FL38 require- Ing basis (as delineated within the current Tech ments. Specs).
- 13) Table 3-11: AV calculation should be based AV results were revised to state results Interms of upon 122.642% Span [vs. 120% as shown]. If [worst-case] RSG only and PUR/SGR Spans, given current 5.0 MPPH flow range Is retained, then the use of (maximum) conversion factors/uncer-AV" calculation should be based upon 117% tainties. Use of current Tech Spec AV of < 43.1%
[and not 120% or 122.6420%). and change to Z' = 3.01 are discussed. [Note that use of originally assumed 116.55% will similarly result Inthe continued use of current <43.1% AV.]
- 14) Tables 3-18A &3-1 8B: For conservatism, use Note was added following computation of Z' term In
[Table 3-18B] Z' term of 9.63 (which Includes Table 3-18A; Tablo 3-18A summary comparison 1.58 bias for Tobar transmitters) for Table 3- was also updated to show Z' = 9.63. 18A (Barton) results.
- 15) Table 3-17: Add further CN reference to "No Page 19 of Ref. 2.9.e was added within reference.
EA for M&E Analysis! for SAL' of 542.2 psig. [Also see Table 2-3, Note (7).] I
- 16) Section 3.3: Clarify "high (or 95%, as applica- Reworded to Include applicability ot 95Y. confi-ble) confidence lever. dence levels only for "power/flow calorimetric func-tions' only for 95% confidence. Assumption 3.2.5 reworded to "generally" specify high confidence level, unless noted otherwise.
- 17) Documentation for Concurrent Engineering HESS Review Documentation (Engineering Re-Review by HESS, as required, should be in- view] added within Attachment A2. LEF &TOO cluded in Attachment Section. changed accordingly.
- 18) Miscellaneous Typos/General Comments Remaining comments dispositionecdresolved, as identified per markup (transmitted separately). required.
FORM EGR-NGGC-0003-2-5 )This form is a OA Record when completed Owner's with and Included a completed Review design package. Owners Reviews may is completed. be processed as stand alone QA records when
CALCULATION NO. ElP-I/INST-1010 REV.2. , PAGE A1-3 ATTACHMENT 2 Sheet 1 of 1 Record of Lead Review IU r_ Design Calculation HNP-1 LINST-1 010 Revision I The signature below of the Lead Reviewer records that
. the review indicated below has been performed by the Lead Reviewer;,
. appropriate reviews were performed and errors/deficiencies (for all reviews performed) have been resolved and these records are Included in the design package;
- the review was performed In accordance with EGR-NGGC-0003.
Ej Design Verification Review [] Engineering Review El Owner's Review 0 Design Review 0 Alternate Calculation Oualification Testing O O" Special Engineering Review WA []YES E N/A Other Records are attached. Chris Georgeson 1v / lao __"_/?/_____7 Lead Reviewer (print/sign) ` Discipline Date t 4 t FORM EGR-NGGC-O003-2-5 This form is a QA Record when completed and included with a completed design package. Owner's Reviews may be processed as stand alone QA records when Owner's Review is completed.
CALCULATION NO. HNP-I/INST-1010 REV. 2 , PAGE AI-4 ATTACHMENT 2 Sheet I of I Record of Lead Review HNP-I I INST-1010 Design Calculation Design Calculation HNP-I I INST-1010 Revision 2 The signature below of the Lead Reviewer records that:
- the review Indicated below has been performed by the Lead Reviewer;
- appropriate reviews were performed and errorsldeficiencies (for all reviews performed) have been resolved and these records are included in the design package;
- the review was performed In accordance with EGR-NGGC-0003.
0 Design Verification Review [I Engineering Review E- Owner's Review 0 Design Review El Alternate Calculation El Qualification Testing E] Special Engineering Review E] YES 0D N/A Other Records are attached. Da-,te-oy 11 Larry Costello Lead Reviewer 'j (print/sign) Discipline Date Item Deficiency Resolution No. N o CoH 0 0 fT FORM EGR-NGGC-0003-2-5 This form is a QA Record when completed and included with a completed design package. Owner's Reviews may be processed as stand alone QA records when Owner's Review is completed.
CALCULATION NO. RNP-I/INST-1010 REV. 3 , PAGE AI-5 ATTACHMENT 2 Sheet I of I Record of Lead Review Design Calculation HNP-1 I INST-1 010 Revision 3 The signature below of the Lead Reviewer records that:
- the review Indicated below has been performed by the Lead Reviewer;
- appropriate reviews were performed and errorsldeficiencies (for all reviews performed) have been resolved and these records are included in the design package;
- the review was performed in accordance with EGR-NGGC-0003.
0 Design Verification Review [-l Engineering Review [] Owner's Review ED Design Review ED Alternate Calculation El Qualification Testing El Special Engineering Review El YES 0 WA Other Records are attached. Larry Costello jA'ý Cvxd.Q I&C 2109/05 Lead Reviewer - (print/vign) Discipline Date Item Deficiency Resolution No. 1 There were other Westinghouse Nuclear Safety Added. Advisory Letters related to SG Water Level Uncertainties, including NSAL-02-03 (2/15/02). NSAL-02.04 (2/19/02), NSAL-02-05 (2/19/02, and NSAL-02-05. Rev. 1, (4/22102). These should be added to Section 2.11 references. 2 All of the uncertainty component values used Added. for the SG Level uncertainties in this Calc are based upon Westinghouse CN-TSS-98-19 except for the PMAp,,,, PMAm pFuse f,, and PMA*,,cvvkn,0oop. The latter terms now depend on calculations within EC 59631 as the source document. A note to this effect would help future tracking of the "source" document- for the SG Level uncertainty values used in the Calc. 3 Believe that WCAP-16115-P should be added Added. to the Calculation Indexing Table under Vendor Documents. 4 Believe that the Westinghouse NSALs on SG Added. Level Uncertainties should be added to the Calculation Indexing Table. FORM EGR-NGGC-0003-2-5 This form is a QA Record when completed and Included with a completed design package. Owner's Reviews may be processed as stand alone QA records when Owner's Review is completed.
CALCULATION NO. UNP-I/INST-1O10 REV. 0 , PAGE A2-1 ATTACHMENT 3 Sheet 1 of 3 Record of Concurrent Review Design Calculation HNP-lIIJNST-10I0 Revision 0 E] Design Verification Review rI En gineering Review El Owner's Review r-Design Review [] Alternate Calculation OQualification Testing
] Special Engineering Review HESS Plant Review Larry F. Costello I&ClElectrical 8/31/00 Concurrent Reviewer (nrintlslanl Disclhline Date II Item No. Deficiency Resolution See Attached Generic MPS Comment Sheet Comments dispositionedlresolved, as required (per 12 pages]. attached Cnmment Sheets).
_____ I ______ I
- I j*) FORM EGR.NGGC-0003-3-5 This form is a OA Record when completed and included with a completed design package. Owner's Reviews may be processed as stand alone QA records when Owner's Review Is completed.
CALCUL1&TION NO. HNP-I /INST-1O10 REV. 0 , PACE A2-2 ATTACHMENT 3 Sheet 2 of 3 Record of Concurrent Review Generic Major Projects Comment Sheet Document Name/No.: liNP-1/11NST-1101. Rev. 0 Project ID: SGRJPUR Reviewed by:NarryNostello OrganizationlDiscipline: HESS/I&C Review Package: (Circle one) 30% 70% I1W16 Other r1Page 8, Sect 3.2.3, states that depen- Parenthetical phrase "(i.e.,a Bias term)' deleted from dent uncertainty components are treated Assumption 3.2.3. for clarity. as a bias. They are algebraically added; however, I consider a bias a term that Is added to the total result; Le., PMA terms. 2 Page 9, Sect 32.10, ItIs not an assump- Assumption 3.2.10 reworded to state that temperature tion that the pressure gauges used for compensated pressure gauges are used at HNP. transmitter calibrations are temperature compensated. 3 Page 8, Sect. 3.2.6, states that "although Assumption 3.2.6 revised to remove stated conclusion of sensor drift has been determined to be Reference 2.11.c, as suggested. Independent of time3 per NSAL-97-O1, I do not believe that CP&L or the Industry necessarily concur with this statement. 4 Page 16, The CSA' equation Is missing CSA' Is correct as written [A' is a sum of squares, as the squared term for A'. shown]. 5 Page 16, Recommend adding "o Added wording, as suggested. conservatively maintain minimum tolerances on S' and R'..." 6 Page 31, Need to correct the math for Table 3-2B was revised to: restate the SAL as N/A; and the T2' Calc; the TA' value Is 1.60% clarify selection of 2.5% for consistency with Table 3-2A. span. This effects the AV' catc. 7 Page 40, Where Is the new "Note6' that New "Note 6* for OPAT eliminated from text and Tech is referenced at bottom of page? Spec mark-up. S term Included directly InTech Spec Table 2.2-1 (without additional Note). B Page 49, Provide the basis for using the Explanation added for 1.5% transmitter drift within Tables 1.5% drift value; I.e., calibration history of 3-1DA thru 3-10C and 3-18A &3-18B. the transmitters. 9 Page 49. Might note that the 'worst Clarifying note added to Summary Tables as part of case3 values for the bias terms were resolution to Comment 8 (above). conservatively selected over the full Instrument span. L L &
CALCULATION NO. mNP-1/INST-1010 "EV. 0 , PAGE A2-3 ATTACHMENT 3 Sheet 3 of 3 Record of Concurrent Review 43.1% AV. (Also see Lead DV Comment 13 resolution.) 11 Page 57, delete the extra given thel In Deleted wording, as suggested. para above the table. 12 Page 62, AVm AV = 127.4 will Added wording, as suggested. conservatively be retained....'bi. 13 Page 62. Provide a brief explanation of Table 3-15 was revised to add wording to first paragraph why S.= 0. and to new paragraph before V computation. 14 Page 74, Need to explairtreconcile the Table 3-23, Uncertainty Parameters Note 1was clarified difference Inthe density effects between by deleting first sentence. Original wording was not clear the Westinghouse cale and HNP-IaiNST- (as Westinghouse did not perform a PURISM CN for this 1030. trip function [RWST Low-Low Level]). 15 Page 76, Provide more thorough basis Table 3-23, Uncertainty Parameters Note 3 was clarified for changing the drift value; i.e.. the 30 by deletion of 30-month INST-1 030 assumption. Aparen-month max surveillance frequency Is thetical reference to INST-1 030, Section 5.1A.2 was wrong. Transmitters are calibrated every retained within Note 3. RFO. 17 Page 79, Add "for this permissive" after Added wording, as suggested. Ochanges" in last sentence. 18 Page 80, Add "for this permissive" after Added wording, as suggested.
"changes" Inlast sentence.
19 Clarify basis for OTAT and OPAT allow- Clarification was provided within Tables 3-5 & 3-6 to ad-able Tech Spec sensor error associated dress the following: with RTD measurements. Relate this " S'*w,,w, terminology [used to describe RTD sensor sensor error value and normalization errors contained InWestinghouse CN] was clarified to process to current acceptance criterion/ clearly explain that Westinghouse CN assumptions plant practices contained within EST-1 04 were based upon a channel that was already andlor EPT-156. normalized. Paragraph at top of Page 39, In Table 3-5 [OTATIJ, was augmented to specify INST-1 049/EST-1 04 acceptance criterion for RTD calibration accuracy and drift, as well as to defne a corresponding PURFSGR Tech Spec sensor error term of 1.3% &Tspan.
" Rack drift component within Allowable Value [per R'a-,]
was confirmed against current plant practices/ accep-tance criterion [i..e, relative to EPT-156 criterion on need to renormalize (-1 to +3% AT tolerance is used by EPT-1 56; -1% selected as the applicable conservative tolerance, given that +3% will effect an earlier trip)].
Attachment 8 Shcet I of I Calculation lndcxing Tabe Calculation No. MNP-XIINST-10l0 Page No. A-1 Revision 0 Document Number or Basis for Type of Document Tag Number Document Title Cross Reference Technical Speci- Table 2.2-1; Reactor Trip System TS Compliance fications Bases 2.2 Instrumentation Trip Setpoints Table 3.3-41 Engineered Safety Features Bases 3/4.3.1 & Actuation System Instru-3/4.3.2 mentation Trip Setpoints FSAR Sections 1.8 Conformance to: Consistency with RG 1.105 Rev. 1 Chapter 15 safety analyses assumptions 7.1.1 Identification of Safety and licensing com-Related System mitments 7.2 Reactor Trip System 7.3 Engineered Safety Features System 15.0.6 Trip Points and Time De- * - lays to Trip Assumed in Various Sections of Accident Analyses
- Chapter 15 discuss analyses which rely 15.0.7 Instrumentation Drift and on the RTS/ZSFAS Trip Calorimetric Errors - functions (subject to Power Range Neutron Flux this calculation);
Table 15.0.6-2 lists 15.0.0 Plant Systems and Compo- these functions and nents Available for Miti- the analyses using gation of Accident Effects theme functions. PO Procedures CC Applicable Functions Calibration and Sur-NST-Z0003 thru Containment Pressure veillance Procedures MST-I0006; for TS c*HBance MST-X0236 thru MST-X0239 MST-XO007 thru Main Steam Pressure MST-10015p MST-10125 thru MST-10133 MST-I0016 thru Main Steam/Feedwater Flow MST-100211 Mismatch - MST-X0134 thru Procedure References MST-X0139 does not include Time Response Testing for MST-X0023 thru SG N-R Level these Instrument MST-X0036; Functions. MST-X0143 thru MST-20151, and MST-10175 thru MST-X0177 ENO,1Re. 0 .g2o.2 ENP-01 I Rev. 10 Page 27 of 28
Attachment 8 Sheet I or I Calculation Indexing Table Calculation No. JilP-X/INST-lOlO Page No. -A3-2 Revision 0 Document Number or Basis for Type of Document I Tag Number I Document Title Cross Reference POX Procedures ** Applicable Function: Calibration and Sur-(Centtd) veillance Procedures UST-X0037 thru RCS Delta T/Tavg for TS cozplianco MST-X0039; MST-10140 thru MST-10142 MST-10268 thru Lo-Lo Tavg P-12 Interlock MST-X0270 MST-10040 thru RWST Level MST-X00431 MST-10204 thru MST-X0207 MST-10044 thru NIS Power Range MST-X0047; and MST-X0070 MST-10163 tbru
)ST-XO166 MST-I0048 and NIS Intermediate Range MST-XD049; MST-I0167 and MST-10168 MST-10050 and NIS Source Range NST-XO0511 MST-X0169 and MST-I0170 MST-X0052 thru Pressurizer Level MST-10054i MST-Z0208 thru MST-10210 MST-X0055 thru Reactor Coolant Flow MST-ZO063i MST-X0152 thru NST-X0160 MST-10067 thru First Stage Turbine Im-NST-10068 pulse Pressure MST-X0119 tbru Pressurizer Pressure MST-X01211 MST-10122 thru MST-X0124 MST-10260 thru T-G Low Fluid Pressure MST-X0262 MST-X0263 thru T-0 Throttle Valve Closure MST-10266 Page 27 of 28 Rev. 10 ENP-01I ENP-Ol! Rev. 10 Page 27 of 28
Attachmcnt 8 Sheet I of I Calculation Indexing Table Calculation No. MOTP-VI/NST-1010 Page No. ._A3-3___ _ Revision .0 Document Number or Basis for Type of Document Tag Number Document Title Cross Reference POM Procedures ** Alpplicable Function: Calibration and Our-(Cont'd) veillance Procedures MST-E0073 RCP Bus Underfrequency for TS conpliance MST-E0074 RCP Bus Undervoltage UST-K0045 and 6.9KV E-Bus Undervoltage MST-E0075 P0K Procedures EPT-008 Intermediate and Power Additional Calibra-Range Detector Setpoint tion/Surveillance Determination Procedures for Chan-nel Normalization or EPT-009 Intermediate Range Detec- other Scaling tor Setpoint Verification EPT-156 Reactor Coolant System AT Scaling at 100% Reactor Power Design Basis DBD-301 Reactor Control and Pro- RTS/ESPAS Design Documents tection System Criteria DBD-313 Time Response DBD-314 Plant Parameters Document wUR/sOR-project re-lated UTAPPD will be Incorporated into DBD-314 Pesigrn masxsi/ Attachment to 2narr1s nuclear alant SCR/ MRTN/Z8AZ D*Nlgn AS-Plant Parameters MMP-FI/NSA-0034 PUR Uprate Fuel Analysis ference for P7R/SGR Document Plant Parameters Document Implementation In-(UFAPPD) eluded in UFAPPD Tables 2-2 and 2-18 NGG Procedure EGR-NGGC-0153 Engineering instrument NGO standard for In-Setpoints strument uncertain-ties ENP-01 I Rev. 10 Page 27 of 28
Attachmcnt 8 Sheet I of I Calculation Indexing Table Calculation No. HNP-X/XNST-1010 Page No. -A3-4 Revision 3 Document Number or Basis for Type of Document Tag Number Document Title Cross Reference Vendor Document WCAP-15249 Westinghouse Protection Westinghouse method-System Setpoint Methodo- ology to support TS logy ... (for Uprate to compliance and FSAR 2912.4 MWT-NSSS Power and coagtmnts; *Five-Replacement Steam Genera- Columnw Terms and tors) Dases still applica-oblr to I=D Tech Spec. Vendor Document rCQL-355 Westinghouse Setpoint Original Westinghouse Methodology for Protection methodology to sup- [EHDRAC Systems Shearon Harris ... port TS ccmwliance 1364-0530672 and rSAR com=itments Vendor Document WCAP-10183 Setpoint Study ... Shearon Original Westinghouse Harris Nuclear Plant, report used during [EMDRAC November 1982 Initial plant tests 1364-051149] and oporationj (historical reference) includes RTS/ESFAS sotpoint values Vendor Document WCAP-16115-P Westinghouse Steam Referenced 'Source' Generator Level Document for design Uncertainties Program inputs within this site document Vendor Document TB-04-12 Westinghouse Technical Referenced 'Source' Bulletin Steam Generator Document for design Level Process Pressure inputs within this Evaluation site document Vendor Document NSAL-02-03 Westinghouse Nuclear Referenced Vendor [NSAL] NSAL-02-04 Safety Advisory Letters Documents related to NSAL-02-05 associated with Steam design inputs within NSAL-03-09 Generator Water Level this site document Uncertainties Vendor Document Westinghouse Precautions, Limitations Westinghouse document PL&S Document and Setpointu for Nuclear includes RTS/ESFAS Steam Supply Systems setpoint values [EMDRAC 1364-0538721 ENP-O011 Rev. 10 Page 27 of 28
Attachment 8 Sheet I of I Calculation Tndcx in! Table Calculation No. IINP-Z/INST-1010 Page No. -A3 -5 Revision 0 Document Number or Basis for Type of Document Tag Number Document Title Cross Reference Vendor Document CN-TSS-98-19 Westinghouse WNPPURISGR- Referenced *Source' [Calc Note] related Xnstrument Uncer- Calculations for do-N-TSS-98-33 tainty Calculations for sign inputs within CN-SSO-99-3 RTS/ESFAS Trip Functions this site document CN-SSO-99-5 CN-SSO-99-7 CN-SSO-99-8 CN-SSO-99-13 CN-SSO-99-14 CN-SSO-99-15 CN-SSO-99-16 CN-SSO-99-17 CN-SSO-99-18 CN-SSO-99-32 CN-SSO-99-33 Site I&C Calcula- Applicable Function: tions HNP-X/INST-1002 RCS Flow Calculations associ-ated with Includes INP-I/INST-1003 Pressurizer Pressure RTS/ESFAS setpoints/ RWST Level p functions MIP-I/INST-1030 and ZQS-2 Site I&C Calcula- Applicable Function: tions (Cont8d) HNP-X/INST-1045 SG N-R Level Calculations associ-ated with includes HNP-VIXNST-1049 RCS N-R Tewerature RTSIESFAS sotpoints/ VNP-X/INST-1054 T-G Throttle Valve Closure trip functions M;P-I/INST-1055 T-G Low Fluid Pressure E2-0010 RCP Bus Undervoltage E2-0011 RCP Bus Underfrequency E2-0005.09 6.9KV E-Bus Undervoltage (Degraded Grid voltage) 0054-JRG PSB-1 Lons of Offsite Power Relay Settings ENP-011 Rev. 10 Page 27 of 28
Attachment 8 Shect I of I Calculation Indexing-Table Calculation No. MNP-I/INST-101o Page No. .. A3--6 Revision 0 Document Number or Basis for Type of Document Tag Number Document Title Cross Reference Site Scaling N22licable Function: Calculations Xbstrument Channel SC-N-040 thru SG N-R Level Scaling Documents 048; and SC-N- applicable for RTSI 175 thru 177 ESFAS Trip Functions. Scaling Calculations SC-N-049 thraU RCS Flow form the basis for 057 values included in SC-N-058 thru Pressurizer Level MT Procedures. 060 SC-N-065 thru Pressurizer Pressure 067 SC-N-073 thru Turbine First Stage 074 Pressure SC-N-078, 107, RCS Delta-T / Tavg and 111 SC-N-089, 090, Main Steamline Pressure 091, and 101 thru 106 SC-N-092 thru Containment Pressure 095 SC-N-108, 109, Steam/Feedwater Flow 110, 112, 113, Mismatch and 114 SC-N-155 thru RWST Level 159 SC-N-174 NI Distables ENP-011 Rev. 10 Page 27 of 28
Attachment 8 Sheet I of I Calculalion Indexing Table Calculation No. ENP-I/INST-10l0 Page No. A3 -7 Revision 0 Document Number or Basis for Type of Document Tag Number Document Tidc Cross Reference Wiring/Xntercon-nection or Other Configuration 2166-B-0508 Setpoint Document *'* _ Drawings Setpoint Document & 2166-B-0432 Instrument List
- Instrument List are shown as historical ZMDRAC 1364- Westinghouse Process Block roforenceso sotpoint 001328 Diagrams data is now currently controlled within the RbMDRAC 1364- Westinghouse Protection MMP engineering data-000864 tbru 878 System Functional Diagrams base system (IMBS),
per ZNP-023. 2166-S-0302 Medium Voltage Relay Set-Sheets 2, 7, 8, tings 20, 23, and 24 BMDRAC 1364- Z.H. Fluid System & Lube 002795 S01 oil Diagram EMDRAC 1364- Wiring Diagramt 003319 Pedestal - Governor 2165-B-0553 S03 Simplified Flow Diagram-DEH Control System ENDRAC 1364- Wiring Diagram: 002724 Terminal Box D- HP Turbine WN_-OI I Rev. 10 Page 27 of 28}}