L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac)

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Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac)
ML091410125
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/31/2009
From:
GE-Hitachi Nuclear Energy Americas
To:
Office of Nuclear Reactor Regulation
References
DRF 0000-0081-4903, L-MT-09-026, TAC MD9990 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008
Download: ML091410125 (26)
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GE Hoa ht Nuclear Energy 3901 Castle Hayne Road Wilmington. NC 28401 Non-proprietaiy Version GEH Number. 0000-0081-6958 MNGP-PRNMS-APRM Caic-2008-NP Revision Number: I Class I DRF Number. 0000-0081-4803 May 2009 Instrument Limits Calculation Nuclear Management Company, LLC (NMC)

Monticello Nuclear Generating Plant Average Power Range Monitor Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC) ttn-pmpfletwy Verskn Revision History REVISION

SUMMARY

0 None i Added non-proprietary notices and removed proprietary information consistent with GEH policies to support submittal to the NRC (10CFR2.390). No changes to technical information were made. Since the changes are administrative, revision bars are not used to indicate the revisions.

Hi

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Nbonpdetay Version Contents:

This document is a supplement analysis data sheet to Reference 1. Included in this document in sequential order are:

  • The setpoint functions for the system,
  • The setpoint function analyses inputs and the source reference of the inputs,
  • The devices in the selpoint function instrument loop,
  • The component analysis inputs and input sources,
  • The calculated results,
  • Input comments and result recommendations (if any),
  • References.

System: Average Power Range Monitor (APRM)

The following setpoint functions are included in this document:

  • APRM Row-Biased Simulated Thermal Power (STP) Scram with Clamp (fLO)
  • APRM Flow-Biased STP Rod Block with Clamp (TILO)
  • APRM Downscale Rod Block 1

00O-0081-6958 MNGP-PRNMS-APRM CaIc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-ppt Version

1. Function: APRM Setdown Scram, Setdown Rod Block, Flow-Biased STP Scram, Flow-Biased Rod Block, Neubron Flux Scram and Downscale Rod Block Setpoint Characterisfcs: Definition Reference(s)

I & -.

Limiting event for the setpoint:

Scram:

The APRM setdown scram setpoint function provides a Event Protection: redundant scram (in addition to IRM) for reactivity transients In the startup mode.

- The APRM flow-biased SIP scram selpoint function is designed to protect against slow reactivity transients.

- The APRM neutron flux-high scram function protects against fast reactivity transients.

Rod Block: Ref. 7.1, "The APRM setdown rod block setpoint function provides a (Section 3.1);

redundant rod block (in addition to IRM) for reactivity Ref 42 transients in the startup mode. (Section "The APRM flow-biased SIP rod block function prevents B 3.32.1) operation significantly above licensed power level; the function precedes a low-biased soram.

" The APRM downscale rod block function provides indication of intmnment failure or insensitivity and assures proper overlap between the neutron monitoring systems.

Function After Earthquake 0 Required 0 Not Required Comment 6 Setpoint Direction

" APRM Setdown Scram 0 Increasing 0 Decreasing

  • APIRM Setdown Rod Block 0 Increasing El Decreasing

" APRM Flow-Biased SIP Scram (TLO) [ Increasing I] Decreasing "APRM Flow-Biased STP Rod Block (1"O) 0 Increasing 0 Decreasing "APRM Flow-Biased STIP Scram (SLO) [ Increasing 0 Decreasing

" APRM Flow-Biased STP Rod Block (SLO) 0 Increasing E] Decreasing Ref 7.1

" APIRM Neutron Flux (Sections Scram [ Increasing 5 Decreasing 3.1.1, 3.12,

" APRM Downscale 3.1.4);

Rod Block [E Increasing 0 Decreasing Ref 3A Ref 62 Singis or Multiple (Sections 3.2.

Channel 4.2.2, 4.3);

- Upscale setpoints [1 Single 0 Multiple Ref 3A

  • Downscale setpoint 0 Single I] Multiple (Section 3) 2

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

AbN-idelwy Version Setpoint Characterlisics: Definition Reflrence(s)

LER Calculation Basis Standand (Consenrative) LER Calculation N or if Multiple Channel Configuration Specific LER Calculation 5 Ref. 1, Ref. 2 Trip Logic for Configuration Specific LER Calculation nla n/a: Not applicable TLO: Two Loop Operation SLO: Single Loop Opemxtion Plant Data: Value Sigma if not 2 Reference(s)

Flow Primary Element a.) Ref 3.1, (Section 4, Item (Ventunr) a.)

  • 1% rated 4.30 and Section 7.3.1); Ref a.) Accuracy (APEA) Recirc flow 5.5 (Item 20) b.) Drift (DPEA) b.) n/a b.) Ref 7.2 (Section 2.1.3)

Flow Process Measurement a.) Ref 7.2 (Section 1.1.3);

Accuracy (PMA) a.)

  • 1.0% rated Ref 5.5 (Item 15) a.) PMA (flow noise) Recim Flow: b.) Ref 7.4 (Section 3.b);

b.) PMA (static head) b.) Negligible Ref. 5.3 Plant Data: Value Sigma if not 2 Reference(s) a.) Ref 3.1, (Section Power Pdmary Element 7.4); Ref 7.2 (Section (LPRM Detector) 2.1.1)

(% Power) a.) +/- 1%; bias 0.49% b.) Ref 2 (Section 4.5.3);

a.) APEAA.. b.) Negligible Comment 16 e-.) Ref 7.2 (Section b.) APEApf.tsv, n fag C.)

  • 0.2% 7days; 2.1.1); Ref 3.1 (Section C.) DPEA bias 0.33 %/7days 7.4)

Power Process Measurement Accuracy (PMA) 8.)Ref 7.2 (Section

(% Powel) 1.1.1); Ref 3.1 (Section a.) Tracking (fixed and flow- 7.4) biased) a.) +/- 1.11% b.)Ref 7.2 (Section b.) Noise (neutron flux) b.) + 2.0% 1.1.1); Comment 13 c.) Noise (STP) c.)

  • 0.0% c.) Ref 7.4 3

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

NAon-pry Version Components (or Devices) In Setpoint Function Instrument Loop:

  • Flow Element 0 LPRM Detector
  • Flow Transmitter
  • NUMAC Chassis:
  • Instrument Loop Flow Electronics (Recirculation Flow Monitor System)
  • Instrument Loop Power Electronics (LPRM, APRM, Trip Circuit) 4

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

MnW-pmpdetwy VerSion 1.1 APRM Setdown Scram ValuelEquation ValuesEquation Current Function PRNMS-CLTP PRNMS-EPU Limits: (% RTP) (% RTP) Reference(s)

Analytdcal Umit n/a n/a Ref 7.6 (Section 1.1)

Tech Spec Allowable Ref 7.6 (Section 1.1);

Value 20% 20% Ref 7.7 (Section 1.3)

Nominal Trip Setpoint 18% 'A (Secion 3)

Ref 7.6 (Section 1. 1);

Operational Lmit 11% 11% Comment 15 1.2 APRM Setdown Rod Block Value/Equation Value/Equation Current Function PRNM8.CLTP PRNMS-EPU Limts: (%RTP) (%RTP) Reference(s)

Analytical Umit n/a n/a Ref 7.6 (Section 1.2)

Tech Spec Allowable Ref 7.6 (Section 1.2);

Value 15% 15% Ref 7.7 (Section 1.3)

Nominal Tdp Setpoint 13% ARef7.6 (Section 3)

Operational Limit n/a n/a Comment 3 1.3 APRM Flow-Biased Simulated Thermal Power Scram with Clamp (TLO)

Value/Equadon ValusiEquation Current Function PRNMS-CLTP PRNMS-EPU Lihits: (% RTP) (% RTP) Reference(s)

Analytical Umit n/a n/a Ref 7.6 (Section 1.3)

Tech Spec Allowable 0 .6 8Wd + 61.6% O.55Wd + 61.5% Ref 7.6 (Section 1.3);

Value Clamped at 116% Clamped at 116% Ref 7.7 (Section 3.3.1) 0.66 VV*d + 59.6%

Nominal Trip Setpoint Clamped at 114% Ref 7.6 (Section 3) 100% (at 82.4% 100% (at 99.1C%

Operatinal Limit Realm flow rate) Recirc flow rate) comment 18a 5

0000-0081-6958 MNGP-PRNMS-APRM CaIc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-pmpflelwy Version 1.4 APRM Flow-Biased Simulated Thermal Power Rod Block with Clamp (TLO)

Value/Equation Value/Equation PRNMS-CLTP PRNMS-EPU Current Function Umits: (% RTP) (% RTP) Reference(s)

Analytical Umit n/a n/a Ref 7.6 (Section 1.4)

Ref 7.8 (Section 1.4);

0.66Wd + 55.6% 0.55W1 + 55.5% Ref 7.7 (Section 3.3.1);

Tech Spec Allowable Value Clamped at 110% Clamped at 110% Comment 22 066Wd + 53.65%

Nominal Tdp Setpoint Clamped at 108% Ref 7.6 (Section 3)

Operational Limit n/a n/a Comment 3 1.5 APRM Flow-Biased Simulated Thermal Power Scram (SLO)

Value/Equation ValueiEquation PRNMS-CLTP PRNMS-EPU Current Function Umits: (% RTP) (% RTP) Refrencea(s)

Analytical Umit n/a n/a Ref 7.6 (Section 1.5) 0.660NW -5.4) 0.55(Wd -5.4) Ref 7.6 (Section 1.5);

Tech Spec Allowable Value +61.6% +61.5% Ref 7.7 (Section 3.3.1)

Nominal Trip Setpoint 0.66%W +54.6% Ref 7.6 (Section 3)

Operational Limit n/a n/a Comment 19 1.6 APRM Flow-Biased Simulated Thermal Power Rod Block (SLO)

Value/Equation ValuelEquation PRNMS-CLTP PRNMS-EPU Current Function Umits: (% RTP) (% RTP) Reference(s)

Analytical Limit n/a n/a Ref 7.6 (Section 1.6)

Ref 7.6 (Section 1.6);

0.6868A -5.4) 05.5(Wd -5.4 ) Ref 7.7 (Section a3.1);

Tech Spec Allowable Value +55.6% +55.5% Comment 22 Nominal Trip Setpoint 0.66Wd +48.6% Ref 7.6 (Section 3)

Operational Limit n/a n/a Comment 3 6

0000-0081-6958 MNGP-PRNMS-APRM Caic-2008-NP, Rev. I Selected PRNM Licensing Selpoints - EPU Operation (NUMAC)

NonpmdetwY Version 1.7 APRM Neutron Flux Scram Value/Equation Value/Equation PRNMS-CLTP PRNMS-EPU Cunent Function Umits: (% RTP) __ RTP) Reference(s)

Ref 7.6 (Section 1.7);

Analytical Limit 125% 125 Ref 7.7 (Section 3.3.1)

Tech Spec Allowable Value 122% 1 Ref 7.8 (Secton 1.7)

Nominal Trip Setpoint 119.5% I I Ref7.6(Secton3) 100% (at 82.4% 100% (at 99.1 %

Operational Limit Recir flow rate) Recir flow rate) Comment 21 1.8 APRM Downscale Rod Block Valuerliquation ValueiEquation PRNMS-CLTP PRNMS-EPU Current Function Umits: (% RTP) (% RTP) Reference(s)

Analytical Limit nla nla Ref 5.8 (Item 10)

Ref 4.2 (Table 3.32.1-1);

Ref 5.8 (Item 10);

Tech Spec Allowable Value 2% 2% Comment 20 Ref 5.8 (Item 10);

Nominal Trip Setpoint 3.5% Ref. 3.4 (Section 8.6.1)

Operational Limit nla nla Comment 3 CLTP: Current Licensed Thermal Power nla: Not applicable RTP: Rated Thermal Power Wd: % Recimulation drive flow 7

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-pdetdy Ver,*n 2.1 Flow Transmitter (cont'd)

Plant Data: Value Sigma Ifnot Reference(s) 2 Calib Temperature Range 65 to 90 OF Ref 3.1(Section 7.2.3.2)

Normal Temperature Range 60 to 104 'F Ref 3.1(Section 7.2.3.2)

Trip Temperature range 60 to 104 OF Ref 3.1(Section 7.2.3.2)

Ref 3.1 (Section 7.2.3.3); Ref 7.1 Plant seismic value rna (Section 3.1); Comment 6 Plant Radiation value negligible Ref 3.1 (Section 7.2.3.2)

Plant Humidity value 20 to 90% Ref 3. 1(Section 7.2.3.2)

Power Supply Variation Ref 3.1(Section 7.2.3.3);

value negligible (Ref 5.5 Item 7)

RFI/EMI value 0 Ref 3.1(Section 7.2.3.3)

Over-pressure value 1332 psig Ref 5.5 (Item 8)

Statio Pressure value 1010 psig Ref 3.1 (Section 7.2.3.3)

Drift. Value Sigma If not 2 Reference(s)

Ref 3.1 (Section 7.2.3.2); Ref 4.1(-Table 3.3.1.1-1.

Current Calib. Interval 92 days [:lIncludes exba 25% n/a SR 3.3.1.1.9)

Desired Calib. Interval 24 mo. I-lnoludes extra 25% n/a Ref 5.5 (Item 2)

Drift Source OVendor [Calculated n/a Ref 6.6 (Section 6)

Ref 6.6 (Section 6)

Ref 1.Ref 2 Drift Value +/- 0.2% URL 130 months Comment 7 9

0000-0081-6958 MNGP-PRNMS-APRM Caic-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-pnx y VWsfon 2.1 Flow Transmitter (cont'd)

Calibration: Value I equation Sigma if not 3 Reference(s)

RefL3.1 (Section As Left Tolerance + 0.3125% Span (+/- 0.05 mA) 7.2.3.5)

As Found Tolerance Ref 5. 1;

(=Leave Alone Tolerance) =ALT Ref 5.5 (Item 16)

Ref 5.4; Input Callbration Tool: Ashcroft Model 2089 n/a Ref. 5.5 (Item 10) 1 0.1% of full scale Ref 5.4; Accuracy (FS-277.3 InWC) Ref 5.5 (item 10)

Resolution I Readability 0.0005 Ref 5.5 (Item 11)

Minor Division n/a Upper Range n/a Temperature Effect Induded in accuracy Ref 5.4 Input Calibration Standard: Deadveight tester n/a Ref 5.5 (Item 13)

Ref 5.2 (Section 5.2.6); Ref 5.5 (Item Accuracy = Input calibration tool accuracy 13); Comment 8 Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Tool: Fluke Model 189 nia Ref 5.5 (Item 9)

Accuracy I- 0.04 mA Ref 5.5 (item 9)

Resolution I Readability 0.005 Ref 5.5 (Item 11 a)

Minor Division n/a Upper Range rina Temperature Effect Induded in accuracy R Output Calibration Standard: Fluke Calibrator n/a Ref 5.5 (Item 14)

Ref 5.2 (Section 5.3.6); Ref 5.5 (Item Aocurac =Input Calibration Tool accuracy 14); Comment 8 Resolution I Readability Minor Division Upper Range Temperature Effect Application Specific Input: Value Sigma If not 2 Rererenoe~s) n/a 10

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Ak-np- Version 2.2 Flow Electronics (cont'd)

Plant Data: Value Sigma iNnot 2 Reference(s)

Ref. 3.1 (Section 7.2.2)

Calib Temperature Range 72 to 78 OF n/a Ref 5.5 (Item 3)

Normal Temperature Range 72 to 78 &F n/a Ref. 3.1 (Section 7.2.2)

Trip Temperature range 72 to 78 OF n/a Ref. 3.1 (Section 7.2.2)

Ref. 3.1 (Section 7.2.2);

Ref 7.1 (Section 3.1);

Plant seismic value n/a nra Comment 6 Plant Radiation value negligible n/a Red. 3.1 (Section 7.2.2)

Plant Humidity value 20 to 90% nra Ref. 3.1 (Section 7.2.2)

Power Supply Variation value negligible nra Ref 5.5 (Item 7)

RFI/EMI value negligible nra Ref. 3.1 (Section 7.2.2)

Over-pressure value n/a n/a Comment 5 Static Pressure value n/a rna Comment 5 Drift: Value Sigma if not 2 Reference~s)

Ref. 3.1 (Section Current Calib. Interval 92 days I-lncludes extra 25% W/a 7.2.2)

Ref 7.3 (Section 5.1.2.2-1);

Desired Calib. Interval 24 mo. [llncludes extra 25% n/a Ref 5.5 (Item 2)

Drift Source IjVendor 0Calculated n/a Ref. 1; Ref. 2 Drift Value Not specified; If 11 0 (% rated driveflow) = +/- 0.122 mAdc 16 months I Ref. 1; Ref. 2 12

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-jnpdetwy Venn 2.2 Flow Electronics (conrd)

Calibration: Value I equation Siama if not 3 RtfeJnces)

Ref. 7.3 (Section As Left Tolerance n/a 5.1.221)

As Found Tolerance Ref. 7.3 (Section

(=Leave Alone Tolerance) rita 5.1.2.2.1)

Ref. 7.3 (Section Input Calibration Tool: Internal to NUMAC n/a 5.1.22-1)

Ref. 7.3 (Section 5.1.2.2.1);

Accuracy +(1.1)*0.192% units on 125%scale Comment 14 Resolution I Readability included in accuracy Minor Division Included in accuracy Ref. 7.3 (Section Upper Range 125% n/a 5.1.2.2.1)

Temperature Effect Included In accuracy Ref. 7.3 (Section Input Calibration Standard: incduded in calibration tool 5.1.2.2.1)

Accuracy nra Resolution I Readability rna Minor Division n/a Upper Range n1a Temperature Effect n/a Ret. 7.3 (Section Output Calibration Tool: n/a 5.1.2.2.1)

Accuracy Resolution I Readability Minor Division Upper Range Temperature Effect Output Calibration Ref. 7.3 (Section Standard: nra 5.1.2.-21)

Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect AppWlcatlon Specific Input: Value Sigma If not 2 Reference(s) n/a 13

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Nony-ppety Version 2.3 Power Electronics (LPRM, APRM, Trp Circuit) (cont'd)

Plant Data: Value Sigma if not 2 Reference(s)

Ref. 3.1 (Section 7.2.2)

Calib Temperature Range 72 to 78 OF r/a Ref 5.5 (Item 3)

Normal Temperature Ranige 72 to 78 OF rna Ref. 3.1 (Section 7.2.2)

Trip Temperature range 72 to 78 OF nra Ref. 3.1 (Section 7.2-2)

Ref. 3.1 (Section 7.2.2);

Ref 7.1 (Section 3.1);

Plant seismic value n/a rna Comment 6 Plant Radiation value negligible rna Ref. 3.1 (Section 7.2.2)

Plant Humidity value 20 to 90% rta Ref. 3.1 (Section 7.2.2)

Power Supply Variation value negligible rna Ref 5.5 (Item 7)

RFI/EMI value negligible ria Ref. 3.1 (Section 7.22)

Over-pressure value n/a ria Comment 5 Static Pressure value nta nfa Comment 5 Drift: Value Sigma If not 2 Reference(s)

Ref. 4.1 (Table 7 days [lIncludes 3.3.1.1-1, SR Current Calib. Interval extra 25% n/a 3.3.1.1.2)

Ref. 4.1 (Table 7 days :Includes 3.3.1.1-1, SR Desired Calib. Interval extra 25% n/a 3.3.1.1.2)

Drift Source Rcndor f-Calculated n/a Ref. 1, Ref. 2 Drift Value Ref. 6.4 (Section S(%power) +/-.Q5% FS1700 hours 4.3.3.3) 15

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-pdet&y Version 2.3 Power Electronics (LPRM, APRM, Trip Circuit) (cont'd)

Calibration: Value I equation Sigma I not 3 Reference~s)

Incuded in APRM calibration As Left Tolerance AGAF Comment 11 Ref a31 (Sections As Found Tolerance 7.2.1.56 7.6.6);

(=Leave Alone Tolerance) = ALT Comment 11 Input Calibration Tool: nla Comment 11 Accuracy Resolution I Readability Minor Division Upper Range Temperature Effect Input Calibration Standard: nla Comment 11 Accuracy Resolution I Readability Minor Division Upper Range Temperature Effect Output Calibration Tool: nfa Comment 11 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Standard: nla Comment 11 Accuracy Resolution I Readability Minor Division Upper Range Temperature Effect I Application Specific Input; Value Sigma If not 2 Reference(s)

Ref. 6.1 (Sections Minimum no. of LPRMs per 3.1.2, 4.1.5);

APRM Channel 14 of 24 nla Ref. 6.3 (Table 1)

APRM Gain Adjustment Factor Ref 3.1 (Sections (AGAF) +/- 2% RTP 3 4.7. 7.6.6) 16

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-pýp y Version

4. Comments and Recommendations:
1. Unless specifically identified as Obias" errors in this document, all instrument uncertainty errors will be considered to be random in nature, even when the 0:" symbol is not shown.
2. Some plant specific Information has not been provided or Is not currently available In the current MNGP sctpoint document, but is considered unnecessary because the effects of this Informatlon are Included within the Instrument accuracy values or are not necessary for setpolnt evaluation
3. STA evaluations am not performed for rod blocks or permissives per GEH setpoint methodology (References I and 2), such as the APRM Rod Blocks. Therefore, the Operational Limits (OLs) are not applicable.
4. Seismic effect, radiation effect, humidity effect, power supply effect, Radio Frequency Interference / Electromagnetic Interference (RFI/EMI) effect, and insulation resistance effect errors are marked Onegligible" or'included in accuracy" and are considered to have negligible impact on the manufacturer's accuracy terms if they are not identified separately.
5. Per References I and 2, overpressum effects am applicable only to pressure measurement devices (e.g., differential pressure transmitters), and static pressure effects are applicable only to differential pressure measurement devices. These effects are marked "na' for other devices or not considered.
6. Per Reference 7.1, the APRM Flow-Biased Simulated Thermal Power Scram setpoint does not perform a protective function credited in a design-basis safety analysis. Similarly, the Setdown Scram and Rod Block setpoints are not credited in any safety analysis. Per Reference 7.1, PRNM installation does not change the neutron flux setpoint function. In general, as indicated in Reference 3.1, the ARPM scram and rod block functions do not consider seismic conditions.

Therefore, the Seismic Effect for the flow transmitters and associated electronics is not considered in this evaluation.

7. The current approach In GEH setpoint calculation methodology treats the Flow Transmitter Drift for this Instrument to be a 2-sign. value.
8. The error of the calibration standard used to calibrate a calibration tool is conservatively assumed to be equal to the error of the calibration tool.
9. The accuracy of the flow electronics is not given in the NUMAC specifications, and if

] The combined error for the loop flow electronics is *10.122 mA at 2G.

(Reference 7.3).

10. The NUMAC electronics are typically located in the Control Building at BWR plants, where the radiation dose is expected to be negligible. At MNGP, the electronics will be located in the Administration Building, which is also expected to have negligible radiation dose.
11. The APRM subsystem is calibrated on-line weekly (Reference 4.1) using the AGAF process, where the gain of the APRMs is adjusted to read the Core Thermal Power (CTP) determined by the Process Computer (P/C). within a specified As Left Tolerance. ((

fl (Reference 7.5).

Thus, the only calibration error to consider for the APRM electronics sub-loop is the As Left Tolerance specified by the AGAF process.

18

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-Amp Versfon 12.1[

]As indicated in Section 3, the NTSP for TLO is 0.55 Wd + 59.5%, indicating an intercept of 59.5%.

The NTSP for SLO, 0.55Wd +55.6%, has an intercept of 55.6%. [

JJ The resulting TLO to SLO setting adjustment is 7.09. Because the Setting Adjustment is programmed into the NUMAC equipment to one decimal place, each calculated number is rounded up to one decimal place for conservatism. This adjustment may be used in the implementation of the new NU MAC equipment.

13. The PRNM Introduces APRM Setdovn trip (scram) and rod block setpoints. Per Ref. 6.2, the scram is based on the neutron flux signal and the rod block on the STP signal. The neutron noise value provided in Ref. 7.2 is conservatively applied to the Seldown rod block as well as the Setdown scram selpoint evaluation.
14. Complete inputs are unavailable for the Flow Electronic calibration errors for all Maintenance and Testing Equipment (M&TE) to be used at MNGP. Therefore, the Flow Electronics calibration errors are based on using errors that are 10% higher than the errors for assumed calibration tools (Reference 7.3). Moreover, the error of the calibration standard used to calibrate a calibration tool is conservatively assumed to be equal to the error of the calibration tool.
15. For the APRM Setdown Scram, the Operational Limit (OL) was set equal to the RTP at which the operator must switch to "Runs. Ref 5.6 indicates that at a minimum. APRMs must read 5%.

Discussions with plant personnel indicate that the switch to Mode 1 would occur not later than W to 11% power (Ref 5.5, Item 17) to avoid plant rip from the IRMs at high power. As indicated in Ref. 7.7 (Sections 1.3, 3.3.2), the APRM Setdown Scram is not affected by EPU and the IRM/APRM overlap is not significantly affected by EPU. Thus, the OL value is unchanged for EPU. Per GEH setpoint methodology (Reference 1 and Reference 2), ((

16. [

)) (Reference 2 Section 4.5.3)

17. Some of the references were submitted to GEH in support of related tasks, e.g., T0500 or the CLTP report Identified as Ref 7.6..
18. The Operational Limit in the non-cdamped region is determined by maintaining the same margin between the NTSP at the intercept point and OL as between the NTSP and OL in the clamped region.
19. An STA evaluation is not performed for single loop operation due to the rarlty of plant operation in this configuration; thus, the OL is not applicable.
20. Ref 7.7 demonstrated that the AL for the fixed APRM Neutron Flux and Setdown scrams and the AVs for the i'ked Setdown Rod Block do not change with EPU implementation. The APRM Downscale Rod Block provides an indication of equipment function and overlap of neutron monitoring systems. As indicated in Ref. 3.4, the AV for the Downscale Rod Block is an operational choice to detect a malfunctioning APRM. As such, the AV is anticipated not to change with EPU.
21. The Operational Limit is the same as that used for the damped region of the Flow-Biased STP scram.
22. The Allowed Value may be retained in the Technical Specifications or a supporting document such as the Technical Requirements Manual, as indicated in the references. The calculations were performed based on the AV point values indicated; a 0S= sign accompanies the Technical Specifications values.

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NUMAC)

Non-pmpdetw* Verskmn

23. The setpoint values for EPU were calculated assuming installation of PRNMS. If desired, selpoints that am more conservative, (i.e., have greater margin to the AL) than the calculated results provided in Section 3, may be retained.
24. Transfer functions used in this calculation:

flow Transmitter Output (mA) linearly converted from input OnVWC).

Flow Electronics: Output proportional to the square root of the two inputs, which are then sumned.

Power Electronics: Output is proportional to the average of the inputs and a comparison of the APRM signal with the flow-biased reference Is nade.

20

0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NNUMAC)

Non-praetý y Versfon

5.

References:

1. NEDC-32889P, Rev. 3, Class 3, "General Electric Methodology fbr Instrumentation Technical Specification and Setpoint Analysis', November 2002.
2. NEDC-31336P-A, Class 3, "General Electric Instrument Setpoint Methodology", September 1996.
3. Current applicable Monticello Nuclear Generating Plant setpoint calculations:

3.1. CA-96-224, Monticello Nuclear Generating Plant Calculation, "Average Power Range Monitor (APRM) Flow-Biased Upscale Scram and Rod Block", Rev. 1,01/09107.

3.2. CA-96-059, Monticello Nuclear Generating Plant Calculation, "APRM-Recirc Flow Instrumentation Calibration', Rev. 3. 08/23107.

3.3. Not used.

3.4. CA-05-153, Monticello Nuclear Generating Plant Calculation, "Average Power Range Monitor (APRM)-Dovmscale Rod Block', Rev. 0, 01120/08.

4. Monticello Nuclear Generating Plant Ucensing and related documents:

4.1. Monticello Nuclear Generating Plant Technical Specifications, as revised through Amendment 146.

4.2. Monticello Nuclear Generating Plant Technical Requirements Manual (IRM), as revised through Revision 2.

5. Current applicable Monticello Nuclear Generating Plant procadures/documents:

5.1. Procedure 0026, Monticello Nuclear Generating Plant Procedure, "APRM-Recirc Flow Instrumentation Calibration' (Temporary Change Number 038-B), issued 11/02/07.

5.2. Engineering Standards Manual ESM-03.02-APP-I, Monticello Nuclear Generating Plant, "Appendix I (GE Methodology Instrumentation and Controlsy', Rev 4.

5.3. Dwg NX-20032-1 Rev A (Permutit Dwg 556-33523 "Details 28' Recirculation Flow Element', Rev 3, dated 7126/83).

5.4. I&M008-10080-2/06, "Ashcroft Digital Test Gauge Operating Instructions", 02106.

5.5. MNGP Completed Design Input Request (File MNGP-GE-M-019), transnitted by letter from Rick Rohrer (NMC) to F. Helin (GEH), Transmittal of Completed Design Information Transmittal (DIT), # 524, 12/20/07 5.6. Monticello Nuclear Generating Plant Technical Operations Manual Section C.1, "Startup Procedure', Rev. 56.

5.7. Monticello Plant Technical Manual, Fluke Model 189 Digital Mutimeter Instruction Manual, NSP Technical Manual Number NX-60259 (Vendor document Fluke Model 187

& 189, August 2000, Rev 01).

5.8. MNGP Completed Design Input Request (File MNGP-453-GEH) " DIR T0500 Response Rev.3", transmitted from S. Hammer (MNGP) to C. Hinds (GEH), 01/16/08.

21

0000-0081-6958 MNGP-PRNMS-APRM CaIc-2008-NP, Rev. I Selected PRNM Licensing Setpoints - EPU Operation (NNUMAC)

Non-pmpdew Verson

6. Vendor Specifications 6.1. GE 24A5221NF, Rev. 0, "PRNM Requirements Specification', Data Sheet, Monticello, August 3, 2007.

6.2. GE 24A5221, Rev. 15, "NUMAC Power Range Neutron Monitor Systerm", Requirements Specification, January 24, 2008.

6.3. GE 26A6192NF, Rev. 0, 'NUMAC Average Power Range Neutron Monitor Aith DSS-CD", Data Sheet, September 26, 2007.

A.4. GE 2661 92, Rev.3, 'NUMAC Power Range Neutron Monitor with DSS-CD',

Performance Specification, September 28, 2007.

6.5. GE 23A5082, Rev. 1, "NUMAC Requirements Specification", Design Spec, August 9, 1995.

6.6. Rosemount Nuclear specification sheet 00809-0100-4235, Rev. AA, 'Model 1152 Alphaline@ Nuclear Pressure Transmitter, June 1999, provided in Monticello Plant Technical Manual NX-17137.

7- GFH Lattrs I Reports:

7.1. GEH-NE-0000-0076-2388-R1, 'Nuclear Management Company, LLC Monticello Nuclear Generating Plant PRNM Licensing Setpoints-CLTP Operation', December, 2007.

7.2. 'Bases for PMA & PEA Values for NMS Setpoints', BasesNMSPMAPEA2.doc, DRF C51-00217, Y. Dayal, 3/15/99 rintemal GE document not releasable].

7.3. GE DC-4608 Volume XI DCD; Rev. B, 'Design Calculation for NUMAC Power Range Neutron Monitoring System (PRNM)', DRF CS1-00136 (4.42), October 9, 1998 [not releasable].

7.4. GEH Document 'Closure of CAR 6912 for RBM and APRM Setpoint Calculations', file CAR6912CIosureBasis.doc, DRF A74-0001 1-00, 03/19/2002 [internal GE document not releasable].

7.5. GEH Document NMS Setpoint Calculation Procedure for D & QC', DRF 0000-0032-4691 (Section 0000-0044-3648) [not releasable].

7.6. GEH Report 0000-0077-9068 MNGP-PRNMS-APRM Calc-2008, 'Nuclear Management Company, LLC Monticello Nuclear Generating Plant Average Power Range Monitor Selected PRNM Licensing Setpoints-CLTP Operation (NUMAC), Rev 2, March 2008.

7.7. GEH Project Task Report GEH-NE-0000-0061-5947-TR-RO, 'Nuclear Management Company, LLC Monticello Nuclear Generating Plant Extended Power Uprate T0500 Neutron Monitoring System with RBM', February 2008.

22

ENCLOSURE 2 RESPONSE TO NRC FIRE PROTECTION REVIEW BRANCH RAIs DATED MARCH 12, 2009

L-MT-09-026 Page 1 of 5 FIRE PROTECTION RAI No. 1 to Matrix 5, "Supplemental Fire Protection Review Criteria, Plant Systems", of NRR RS-001, Revision 0, Review Standardfor Extended Power Uprates, states that "power uprates typically result in increases in decay heat generation following plant trips. These increases in decay heat usually do not affect the elements of a fire protection program related to (1) administrative controls, (2) fire suppression and detection systems, (3) fire barriers, (4) fire protection responsibilities of plant personnel, and (5) procedures and resources necessary for the repair of systems required to achieve and maintain cold shutdown. In addition, an increase in decay heat will usually not result in an increase in the potential for a radiological release resulting from a fire.

However, the licensee's LAR should confirm that these elements are not impacted by the extended power uprate."

We note that Enclosure 5 to L-MT-08-052, Section 2.5.1.4, "Fire Protection", specifically addresses only item (2) above. Please provide statements to address items (1) and (3) through (5), and a statement confirming no increase in the potential for a radiological release resulting from a fire.

NSPM RESPONSE The increase in decay heat from EPU does not affect the following elements of the fire protection program.

" Administrative controls

  • Fire suppression and detection systems
  • Fire protection responsibilities of plant personnel
  • Procedures and resources necessary for the repair of systems required to achieve and maintain cold shutdown Note: Equipment repair is not necessary for cold shutdown at MNGP at CLTP or EPU conditions.

There are no design basis events for MNGP that involve radiological releases that result from fires at CLTP or EPU operating conditions, and the increased decay heat from EPU will not result in an increase in the potential for a radiological release resulting from a fire from a design basis event. The radiological risks from severe accidents, which include accidents that involve fires, were discussed in Enclosure 15, "Identification of Risk Implications Due to Extended Power Uprate at Monticello", of the LAR.

The fire risks from plant modifications are systematically reviewed in accordance with the existing design change processes. The impacts to the elements of the fire protection program, such as changes to combustible material loading, are evaluated and developed during the modification processes.

L-MT-09-026 Page 2 of 5 FIRE PROTECTION RAI No. 2 The results of the Appendix R evaluation for EPU are provided in Section 2.5.1.4, "Fire Protection," of Enclosure 5 to L-MT-08-052. However, this section does not discuss the time necessary for the repair of systems required to achieve and maintain cold shutdown nor the increase in decay heat generation following plant trips. Please verify that the plant can meet the 72-hours requirements in both Title 10 of the Code of FederalRegulations Part 50, Appendix R, Sections III.G.1.b and Ill.L, with increased decay heat at EPU conditions.

NSPM RESPONSE The Appendix R safe shutdown analysis at MNGP does not require or credit any repair of plant systems for CLTP or for EPU conditions to mitigate an Appendix R event.

According to the EPU Appendix R design basis event analysis, which included the decay heat effects associated with the power increase, the reactor can be brought to cold shutdown conditions within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> of the event. Cold shutdown can then be maintained using the existing plant systems previously designated for this purpose at CLTP conditions.

In accordance with 10 CFR Part 50, Appendix R, Sections III.G.1 .b and Ill.L, the reactor can be brought to a cold shutdown condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> at EPU conditions using the existing alternate shutdown cooling systems designated for mitigation of the Appendix R event and then maintained in cold shutdown.

L-MT-09-026 Enclosure 2 Page 3 of 5 FIRE PROTECTION RAI No. 3 We note that Enclosure 5 to L-MT-08-052, Section 2.5.1.4, "Fire Protection," states that the Appendix R fire event was analyzed for the two cases at EPU conditions. The licensee stated that the operator actions required to mitigate the consequences of a fire are not affected nor is there a need for any new operator actions. Please verify that additional heat in the plant environment from the EPU will not (1) interfere with required operator manual actions being performed at their designated time, or (2) require any new operator actions.

NSPM RESPONSE There are no new operator actions required as a result of the proposed EPU to mitigate the Appendix R fire event, and the existing assumptions for the timing of the required operator actions during an Appendix R event were not changed for EPU.

The governing procedure for operator actions during an Appendix R event is Abnormal Operating Procedure C.4-C, "Shutdown Outside of the Control Room." The remote shutdown is accomplished at Alternate Shutdown System (ASIDS) Panel C-292 on the third floor of the EFT Building, which is accessed via the Plant Administration Building.

The operator actions to place the reactor in a cold shutdown condition are performed at this panel. EPU does not present conditions that interfere with or change the operator actions necessary to achieve cold shutdown for the design basis Appendix R event.

L-MT-09-026 Page 4 of 5 FIRE PROTECTION RAI No. 4 Some plants credit aspects of their fire protection system for other than fire protection activities, e.g., utilizing the fire water pumps and water supply as backup cooling or inventory for non-primary reactor systems. If the MNGP credits its fire protection system in this way, the EPU application should identify the specific situations and discuss to what extent, if any, the EPU affects these "non-fire-protection" aspects of the plant fire protection system. If MNGP does not take such credit, please verify this as well.

NSPM RESPONSE Monticello does not credit the fire protection system in any mitigation sequences for any design basis event; however the fire protection system can be used as a backup to the primary sources of cooling water in severe accident sequences as shown in the table below. The use of the fire protection system in these sequences would be due to failures of various primary makeup systems, and this secondary cooling function is not dependent on reactor power or the plant changes that occur due to EPU. None of these events where the primary cooling functions are lost are postulated to occur simultaneously with a design basis fire event.

Description Fire Protection System Function EPU Effect Loss of Intake Provide backup cooling water to None Structure the "A"RHR Heat Exchanger to bring the reactor to cold shutdown if RHR Service Water flow is lost RPV Makeup Provide alternate injection of None Alternate Injection cooling water to the reactor via the fire water cross-tie to LPCI Emergency Fuel Provide emergency cooling to the None Pooling Cooling spent fuel pool via a hose station or via the RHR System,

L-MT-09-026 Page 5 of 5 REFERENCES

1. NSPM letter to NRC, License Amendment Request: Extended Power Uprate (L-MT-08-052) dated November 5, 2008. (Accession No. ML083230111)
2. Email P. Tam (NRC) to G. Salamon and K. Pointer (NSPM) dated March 12, 2009, "Monticello - Draft RAI from Fire Protection Branch re. Proposed EPU Amendment". (TAC No.MD9990) (Accession No. ML090720057)
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