L-MT-13-019, Calculation 03-036, Revision 1, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer.

Calculation 03-036, Revision 1, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer.

ML13037A202
Person / Time
Site:	Monticello
Issue date:	09/24/2012
From:	Shaun Anderson Xcel Energy
To:	Office of Nuclear Reactor Regulation
References
L-MT-13-019 03-036, Rev 1
Download: ML13037A202 (34)

Text

L-MT-13-019 ENCLOSURE 4 CALCULATION 03-036, REVISION 1, INSTRUMENT SETPOINT CALCULATION - REACTOR LOW PRESSURE PERMISSIVE BYPASS TIMER 29 pages follow

QF-0549 (FP-E-CAL-01), Rev. 7 Pa~qe 1 of 4

& XcelEnergyr Calculation Signature Sheet Document Information NSPM Calculation (Doc) No: 03-036 I Revision: I

Title:

Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer Facility:NMT E]PI Unit: 01 [12 Safety Class: 2 SR El Aug Q El Non SR Special Codes: El Safeguards El Proprietary Type: Calc Sub-Type:

NOTE: Print and sign name in signature blocks, as required.

Major Revisions EC Number: 20651 F1 Vendor Calc I Vendor Name or Code: Vendor Doc No:

Description of Revision: Revision to the Reactor Low Pressure Permissive Bypass Timer setpoint in support of License Amendment 170 and EPU Conditions as analyzed in CA 12-046.

The following calculation and attachments have been reviewed and deemed Z acceptable as a legible QA recordI Prepared by: (sign - (print) Sean Anderson Date: 9/24/12 Reviewed by: (sign)-- ., i (print) Bill Hill Date:

Type of Review: M Design Verification [E Tech Review LI Suitability Review Method Used (For DV Only): Review [] Alternate Calc [] Test Approved by: (sign) ýI(IW /(print) rZL L)/z

• /b Date: /712-p Minor Revisions E N/A EC No: El Vendor Calc:

Minor Rev. No:

Description of Change:

Pages Affected:

The following calculation and attachments have been reviewed and deemed Elr acceptable as a legible CIA record Prepared by: (sign) / (print) Date.

Reviewed by: (sign) / (print) Date:

Type of Review: [] Design Verification [ Tech Review E] Suitability Review Method Used (For DV Only): [] Review [] Alternate Calc El Test Approved by: (sign) /(print) Date:

Record Retention: Retain this form with the associated calculation for the life of the plant.

This reference table is used for data entry into the PassPort Controlled Documents Module reference tables (C012 Panel). It may NOTE: also be used as the reference section of the calculation. The input documents, output documents and other references should all be listed here. Add additional lines as needed by using the "TAB" key and filling in the appropriate information in each column.

Reference Documents (PassPort C012 Panel from C020)

1. Controlled* Document Name Document Doc Ref Type**

Doc? + Type Number Rev INPUT OUTPUT 1 x PROC APPENDIX I (GE METHODOLOGY INSTRUMENTATION & ESM-03.02-APP-I 4 X CONTROLS) 2 03-054 X x CALC DELAY RELAYSDRIFT ANALYSIS, AGASTAT ETR14D3 TIME INSTRUMENT 3 x CALC DETERMINATION OF INSTRUMENT SERIVCE CONDITIONS95-027 2 X FOR INPUT INTO SETPOINT CALCULATION 95-027 _2_X 4 x DRAW CORE SPRAY SYSTEM SCHEMATIC DIAGRAM NX-7833-21-1 78 X 5 x DRAW ELEMENTARY DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM NX-7905-46-2 80 X 6 x PROC ADS SYSTEM 20 MINUTE TIMER TEST 0113-02 11 X 7 x PROC STOPWATCH FUNCTIONAL TEST 1318 04 X 8 x CALC AUTOMATIC DEPRESSURIZATION SYSTEM BYPASS TIMER 12-046 0 X 9 x CALC INSTRUMENT SETPOINT CALCULATION - AUTO BLOWDOWN 03-037 0 X INITIATION TIME DELAY RELAY 10 x LIC PLANT SAFETY ANALYSIS - ACCIDENT EVALUATION USAR-14.07 28 X METHODOLOGY 11 x DBD CORE SPRAY SYSTEM DBD-B.03.01 04 12 x DBD RESIDUAL HEAT REMOVAL SYSTEM DBD-B.03.04 06 13 x DRAW S/D RESIDUAL HEAT REMOVEL SYSTEM NX-7905-46-3 76 14 x DRAW SCHEMATIC DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM NX-7905-46-7 76 15 x LIC MNGP TECHNICAL SPECIFICATIONS (AMENDMENT 170) TECH-SPECS 167 X 16 x CALC SEISMIC ANALYSIS OF AGASTAT RELAY 95-035 0 X 17 _ 1 Record Retention: Retain this form with the associated calculation for the life of the plant.

• Controlled Doc marked with an "X" means the reference can be entered on the C012 panel in black. Unmarked lines will be yellow. If marked with an "X", also list the Doc Type, e.g., CALC, DRAW, VTM, PROC, etc.

Mark with an "X" if the calculation provides inputs and/or outputs or both. If not, leave blank. (Corresponds to PassPort "Ref Type" codes: Inputs I Both =

"ICALC", Outputs = "OCALC", Other / Unknown = blank)

Other PassPort Data Associated System (PassPort C011, first three columns) OR Equipment References (PassPort C025, all five columns):

Facility Unit System Equipment Type Equipment Number MT I RHR Relay 1OA-K95A MT 1 RHR Relay 10A-K95B MT I CSP Relay 14A-K27A MT 1 CSP Relay 14A-K27B Superseded Calculations (PassPort C019):

Facility Calc Document Number Title Description Codes - Optional (PassPort C018):

Code Description (optional) Code Description (optional)

Notes (Nts) - Optional (PassPort X293 from C020):

Topic Notes Text

[]Calc Introduction []Copy directly from the calculation Intro Paragraph or E] See write-up below E-l (Specify)

Record Retention: Retain this form with the associated calculation for the life of the plant.

QF-0549 (FP-E-CAL-01), Rev. 7 Page 4 of 4 XcelEnergy- Calculation Signature Sheet Monticello Specific Information IZ YES [I N/A Topic Code(s) (See MT Form 3805): RATE, NR737

[] YES Z N/A Structural Code(s) (See MT Form 3805):

Does the Calculation:

[] YES Zj No Require Fire Protection Review? (Using MT Form 3765, "Fire Protection Program Checklist", determine if a Fire Protection Review is required.) IfYES, document the engineering review in the EC. IfNO, then attach completed MT Form 3765 to the associated EC.

E] YES Zj No Affect piping or supports? (IfYes, Attach MT Form 3544.)

El YES Z No Affect IST Program Valve or Pump Reference Values, and/or Acceptance Criteria? (IfYes, inform IST Coordinator and provide copy of calculation.)

Record Retention: Retain this form with the associated calculation for the life of the plant.

QF-0527 (FP-E-MOD-07) Rev. 4 Page 1 ofl1 XceI Energy Design Review Checklist EC Number or Document Number / Title / Revision Number: 03-036, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer, Revision 1 Verifier's Name: William Hill Discipline: Engineer DESIGN REVIEW CONSIDERATIONS: Yes No N/A

1. Were the inputs correctly selected and incorporated into design? EL ELI

2. Are assumptions necessary to perform the design activity adequately described and E] LI reasonable? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed? LI ELI

3. Are the appropriate quality and quality assurance requirements specified? EL

4. Are the applicable codes, standards, and regulatory requirements including issue LI and addends properly identified and are their requirements for design met?

5. Have applicable construction and operating experience been considered? LI EL

6. Have the design interface requirements been satisfied? []

Eli LI

7. Was an appropriate design method used? []

8. Is the output reasonable compared to inputs? 1:1

9. Are the specified parts, equipment and processes suitable for the required El 19 application?

10. Are the specified materials compatible with each other and the design environmental LI L]

[

conditions to which the material will be exposed?

11. Have adequate maintenance features and requirements been specified? LI [] [

12. Are accessibility and other design provisions adequate for performance of needed LI LI []

maintenance and repair?

13. Has adequate accessibility been provided to perform the in-service inspection LI LI []

expected to be required during the plant life?

14. Has the design properly considered radiation exposure to the public and plant LI LI []

personnel?

15. Are the acceptance criteria incorporated in the design documents sufficient to allow [] LI LI verification that design requirements have been satisfactorily accomplished?

16. Have adequate pre-operational, subsequent periodic test and inspection [] LID[

requirements been appropriately specified, including acceptance criteria?

17. Are adequate handling, storage, cleaning, and shipping requirements specified? El LI

18. Are adequate identification requirements specified? M]

ELI ELI

19. Are requirements for record preparation, review, approval, and retention adequately ELI ELI specified?

20. Have Design and Operational Margins been considered and documented? M L LI COMMENTS: LI None 0 Attached (Use Form QF-0528) EL In EC Topic Notes Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-0528 (FP-E-MOD-07) Rev. I Sheet _ of _

DOCUMENT NUMBER/ TITLE: 03-036, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer REVISION: 1 DATE: 9/25/2012 ITEM REVIEWER'S COMMENTS PREPARER'S [ REVIEWER'S

1. I RESOLUTION DISPOSITION 1 Input 4.10 is an obscure reference, Incorporated consider making it an attachment 2 OBE seismic conditions need to be Incorporated defined and addressed - calc 95-035 is an appropriate reference 0A~s/

3 Since the normal & trip environmental Incorporated conditions are the same and within the Agastat specs, the normal repeat accuracy should be used but considered as 1 sigma value 4 The setpoint analysis should be Incorporated based on the analytical limit of 19.3 minutes 5 The humidity range from 95-027 has Incorporated changed to 0 - 90%

Reviewer: William Hill Date:9/25/12 Preparer: Sean Anderson Date: 9/25/12 Page 1 of 1

Table of Contents Document Title Number of Pages QF-0549 ..................................................... 4 QF-0527 ..................................................... 1 QF-0528 .......................................................... 1 Table of Contents ..................................... 1 Calculation Body ....................................... 14 Attachment A: Tyco Datasheet ................. 7 Attachment B: License Amendment 170 ....... 1 Total Pages ................................................ 29

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 1 of 14

1. Purpose This calculation performs a setpoint calculation for the Reactor Low Pressure Permissive Bypass Timers 1OA-K95A, 1OA-K95B, 14A-K27A, and 14A-K27B.

This calculation is performed to support the extended calibration and surveillance intervals of the time delay relays as part of the 24-Month Fuel Cycle Extension project.

Revision 1 of this calculation is being performed in support of License Amendment 170, Input 4.14, which removed the lower allowable limit for the Reactor Steam Dome Pressure Permissive - Bypass Timer (Automatic Depressurization System (ADS) bypass timer) of'> 18min', in Table 3.3.5.1-1 of Technical Specification (TS) 3.3.5.1. With the removal of the lower bound the nominal setpoint will be revised to support future EPU operating conditions based on information provided in Calculation 12-046, Rev 0, MNGP Automatic Depressurization System Bypass Timer Extended Power Uprate (Input 4.13).

The setpoint will be revised from a nominal value of 20 minutes to 15 minutes. This will ensure peak cladding temperature (PCT) remains well below the 10CFR50.46 limit for PCT of 2200°F (approximately 15000F)during both current and future EPU operating conditions.

2. Methodology This calculation is performed in accordance with ESM-03.02-APP-I (Input 4.1). The General Electric Setpoint Methodology is a statistically based methodology. It recognizes that most of the uncertainties that affect instrument performance are subject to random behavior, and utilize statistical (probability) estimates of the various uncertainties to achieve conservative, but reasonable, predictions of instrument channel uncertainties. The objective of the statistical approach to setpoint calculations is to achieve a workable compromise between the need to ensure instrument trips when appropriate, and the need to avoid spurious trips that may unnecessarily challenge safety systems or disrupt plant operation.

Drift values for the time delay relays covered by this calculation were determined in Calculation CA-03-054 (Input 4.4).

The methodology for determining instrument setpoints is not described in the USAR or its references. However, USAR Section 7.1.2.2 does state that MNGP is committed to the GE Setpoint Methodology for instrument setpoint calculations associated with safety limits and Technical Specifications.

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 2 of 14

3. Acceptance Criteria The setpoint and instrument settings should be established such that there is a 95%

probability that the constructed Analytical Limit will envelope 95% of the instrument population of interest when all applicable instrumentation uncertainties are considered.

4. Design Inputs 4.1 Engineering Standards Manual ESM-03.02-APP-I, Appendix I (GE Methodology Instrumentation & Controls), Revision 4. The ESM provides plant specific guidance on the implementation of the General Electric guidelines (Reference 10.1) and methodology (Reference 10.2).

4.2 Deleted 4.3 Monticello Component Master List (CML). The CML contains instrument information relating to the installed equipment as listed in Section 6.2.

4.4 Calculation CA-03-054, Revision 0, Instrument Drift Analysis, Agastat ETR14D3 Time Delay Relays.

ADE.Random +/-1.7% Setpoint ADE.Bias +0.2% Setpoint Calibration Interval 24 months +25%

4.5 Deleted 4.6 Deleted 4.7 Calculation CA-95-027, Revision 2, Determination of Instrument Service Conditions for Input into Setpoint Calculations. Data obtained from this input is listed in Section 6.2. The relays included in this calculation are not listed in CA-95-027. Data for LIS-2-3-672A & C, which are also located in the Cable Spreading Room, is used for this calculation.

4.8 NX-7833-21-1, Revision 78, Core Spray System Schematic Diagram.

14A-K27A, B I Agastat ETR14D3N

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 3 of 14 4.9 NX-7905-46-2, Revision 80, Elementary Diagram Residual Heat Removal System.

1OA-K95A, B Agastat ETR14D3N 4.10 Tyco Electronics, Agastat Nuclear Qualified Control Relays - Series EGP/EML/ETR, 4/24/2002 Edition (Attachment A).

ETR14D3N relay 125 VDC, I to 30 minutes Repeat Accuracy - Normal Conditions +/-5% Setpoint Repeat Accuracy - Adverse Conditions +/-10% Setpoint The environments for which the relays are expected to trip are within the vendor defined normal operating conditions of the relay. Therefore, only the repeat accuracy for normal conditions will be considered.

4.11 0113-02, Revision 11, ADS System 20 Minute Timer Test.

As Found Range < 21.7 minutes As Left Range > 19 and < 21 minutes 4.12 1318, Revision 4, Stopwatch Functional Test.

Maximum Allowed Deviation in Test 0.1% Reading (0.06 Sec in 1 Min Test) 4.13 Calculation 12-046, Rev 0, MNGP Automatic Depressurization System Bypass Timer Extended Power Uprate. Data obtained from this input was used to determine an acceptable nominal setpoint to ensure peak cladding temperature (PCT) was limited to well below the 10CFR50.46 PCT of 2200'F (approximately 15007F) for current and future EPU operating conditions.

4.14 License Amendment 170- Removal of lower allowable limit for 'Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive)'. (Attachment B) 4.15 Calculation 03-037 Rev 0, Instrument Setpoint Calculation ADS Blowdown Initiation Time Delay Relay 4.16 USAR-14.07 Rev 29P, Table 14.7 ECCS Injection Timing Parameters Used in ECCS Performance Evaluations 4.17 Calculation 95-035 Rev 0, Seismic Analysis of Agastat Relay

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 4 of 14

5. Assumptions None.

6. Analysis 6.1 Instrument Channel Arrangement Channel Diaaram:

S...........

"'Low-Low Reactor Relay Core Spray/RHR

- Water Level Initiation.

Definition of Channel: Each time delay relay is initiated by the one-of-two-twice low-low reactor water level signal. After the time delay, the relay provides a contact closure to the Core Spray and RHR systems (Input 4.8; References 10.5 and 10.6).

6.2 Instrument Definition and Determination of Device Error Terms 6.2.1 Device 1 6.2.1.1 Instrument Definition Reference Component ID 1OA-K95A, B and 14A-K27A, B Location: Admin Building, 939', CSR 4.3 Panels C-32 and C-33 Manufacturer: Agastat 4.8, 4.9 Model Number: ETR14D3N 4.8, 4.9 Upper Range limit: 30 minutes 4.10 Adjustable Range: 1-30 minutes 4.10 Input Signal: Contact Closure 4.8, 10.5, 10.6 Output Signal: Contact Closure 4.8, 10.5, 10.6 6.2.1.2 Process and Physical Interfaces Calibration Conditions: Reference Temperature: 165 to 90°F 4.7 Surveillance Interval: 30 months 4.4

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision .

Reactor Low Pressure Permissive Bypass Timer Page 5 of 14 Calibration of the time delay relays is required every operating cycle per Input 4.4. A surveillance interval of 30 months (24 months + 25%) is used in accordance with the guidance in Generic Letter 91-04 (Reference 10.8).

Normal Plant Conditions: Reference Temperature: 60 to 104°F 4.7 Radiation: Negligible 4.7 Pressure: Ambient 4.7 Humidity: 0 to 90% 4.7 Trip Environment Conditions: Reference Temperature: 104 0 F 4.7 Radiation: Negligible 4.7 Pressure: Ambient 4.7 Humidity: Oto90% 4.7 Seismic Conditions: Reference OBE Prior to Function 1.476 4.17 OBE During Function 1.476 4.17 Process Conditions: Reference During Calibration: N/A N/A Worst Case: N/A N/A During Function: N/A N/A These relays are not subjected to process conditions (static pressure, overpressure, elevated temperatures, etc.) that would affect the accuracy of the instrument.

6.2.1.3 Individual Device Accuracy Term Value Sigma Reference VA: + 5.0% Setpoint (normal) 1 4.10 ATE: 0 Note I OPE: N/A Note 2 SPE: N/A Note 5 SE: 0 Note 4 RE: 0 Note 7

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 6 of 14 HE: 0 Note 6 PSE: N/A Note 3 REE: N/A Note 3 Note 1: Accuracy Temperature Effect (ATE) data is not specified for these relays. The ATE is considered to be negligible or part of the Vendor Accuracy since the operating conditions are enveloped by the vendor's qualification limits for normal operation.

Note 2: Overpressure Effects (OPE) are not applicable to relays.

Note 3: Error effects due to Power Supply Effects (PSE) and RFI/EMI Effects (REE) are considered negligible for bi-stable electro-mechanical devices (Reference 10.1).

Note 4: Seismic Effects (SE), Section 6.2.1.2 notes the seismic conditions for the relay. These conditions are bounded by the seismic qualified provided by the vendor as described by Input 4.10. Therefore, inaccuracies due to seismic effects are considered to be included in the VA for trip conditions.

Note 5: Static Pressure Effects (SPE) do not apply to bi-stable electro-mechanical devices (Reference 10.1).

Note 6: The operating conditions of the relays are within the vendor specified operating range of the relay (Input 4.10), therefore Humidity Effects (HE) are considered to be included in the VA for trip conditions.

Note 7: Radiation Effects (RE) is not specified for these relays, they are considered to be included In the VA for trip conditions VAN = Vendor Specifications (Normal Conditions)

VAN = +/- 0.05 x 19.3 minutes = +/- 0.965 minutes 2 2 RE )

AN=2 /VA 2 + (ATEJ) + (OPEJ + (P)2+ (ý)2+ (R + + (PSE) 2 +

AL- -2x 2 +02 +02

-0.965 +02 +02 +02 +02 +02 +02 ALN = + 1.93 minutes 6.2.1.4 Individual Device Drift Term Value VD: Not Specified DTE: Not Specified

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 7 of 14 Vendor drift (VD) is not specified. AMonticello specific drift analysis of Agastat ETR14D3 time delay relays was performed (Input 4.4) to determine the 30 month Analyzed Drift Value (AD) for these transmitters. The AD is used in place of both the VD and the DTE (Drift Temperature Effect):

ADE.Random = +/-1. 7% Setpoint ADE.Bi = + 0.2% Setpoint DL.Random= ADE.Random X Setpoint DL.Radom = +/- 0.017 x 19.3 minutes DL.Radom +/- 0.3281 minutes DL.Bias = ADE.Bias X Setpoint DL.Bias = + 0.002 x 19.3 minutes DLBia = + 0.0386 minutes 6.2.1.5 As-Left Tolerance (ALT)

Per Input 4.1, a suggested ALT is determined with the following equation:

ALT = +2 n)J +/ / + C,/

ALT = +/-22 l.932 1( i.-- )

+ (0.02)2

+( 3

+ (0.02 3)

J2 ALT = +/- 3.86 minutes The existing As-Left Tolerance specified in the surveillance procedure 0113-02 (Input 4.11) is +/- 1.0 minute. Since the existing value is more restrictive than the guideline value, the existing ALT of I minute will be used.

6.2.1.6 Device Calibration Error Term Value Sigma Reference C1 : 0.02 minutes 3 Note 1 ClSTD: 0.02 minutes 3 Note 2 ALT: 1 minute 2 Section 6.2.1.5

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 8 of 14 Note 1: The Calibration Tool Error (C1) is considered equal to the As Found tolerance from the functional test procedure (Input 4.12):

C1 = +/-0.1%xReading C1 = +/-0.001x19.3 minutes C1 = +/-0.0193 minutes Note 2: In accordance with Input 4.1, the calibration standard error (CISTD) is considered to be equal to C1.

Since calibration term values are controlled by 100% testing, they are assumed to represent 3-sigma values. Individual calibration error terms are combined using the SRSS method and normalized to a 2-sigma confidence level.

1 2+E IT 2 +AT2 CL=+/-2xE + - ALT C0.022 0.022 12 (3 =+/-2x 3 2 CL =+/- I minute 6.3 Determination of Primary Element Accuracy (PEA) and Process Measurer Accuracy (PMA)

There are no PEA or PMA inaccuracies associated with these relays.

PMA=O PEA = 0 6.4 Determination of Other Error Terms Term Value Indicator Readability/Operator 0.02 Reading Error (ORE)

Resistors, Multiplexers, etc. 0 Software Errors 0 Degradation of Insulation Resistance 0 (IRE) I An ORE equal to the Calibration Tool Error is applied for readability and operator reaction time.

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 I Reactor Low Pressure Permissive Bypass Timer Page 9 of 14 6.5 Calculation of Allowable Value and Operating Setpoint 6.5.1 Allowable Value (AV):

From Input 4.13, it can be seen that for the bounding scenario of RWCU for MELLA+ with a gate valve a time of 1579 seconds is required to reach 2200° F.

Input 4.13 also shows that it takes approximately 1350 (22.5 minutes) seconds to reach 15000 F. In order to provide sufficient time to cool the core, the actuation of ADS should occur prior to reaching 1500° F, therefore additional consideration is given for the following delays in the ADS initiation: from Input 4.13 a delay of 36 seconds from time 0 of the scenario is taken for initiation of the low low level signal, from Input 4.16 the time required for ECCS pumps to reach rated speed is 18 seconds, from Input 4.15 the ADS timer delay is 138 seconds. Therefore an analytical value of 1158 seconds will be used.

1350s - 36s - 18s - 138s = 1158s (19.3 mins)

Analytical Limit (AL): <19.3 minutes Term Value (Minutes) Sigma Reference ALT 1.0 2 Section 6.2.1.3 CL 1.0 2 Section 6.2.1.6 PMA 0 2 Section 6.3 PEA 0 2 Section 6.3 IRE 0 N/A Section 6.4 ORE 0.02 2 Section 6.4 AVu = AL-(1-4)(VALT + CL2 + PMA 2 + PEA 2 + IRE2 + ORE2 )+ bias terms 2

AVu = 19.3-(. 6 4 5 )(4I.02 +1.02 +02 +02 +02 +0.022)+0 2

AV. = 19.3 -1.163 AV, = 18.13 minutes As a result of CR 02001013 (Reference 10.9), a new Technical Specification Trip Setting is chosen to bound the As Found values (Refer to Section 6.5.5.).

Conservatively rounding down the calculated AV, the new Technical Specification trip setting will be considered the AV for this calculation.

AVu = 18.0 minutes

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 I Reactor Low Pressure Permissive Bypass Timer Page 10 of 14 6.5.2 Nominal Trip Setpoint (NTSP)

Term Valve (Minutes) Sigma Reference ALT + 1.0 2 Section 6.2.1.3 DLRandom + 0.3281 2 Section 6.2.1.4 DL.Bias + 0.0386 NA Section 6.2.1.4 CL + 1.0 2 Section 6.2.1.6 PMA 0 2 Section 6.3 PEA 0 2 Section 6.3 IRE 0 NA Section 6.4 ORE + 0.02 2 Section 6.4 RAVBIas 0 NA Section 6.5.1 (1.645 (. 2 2 2+ R R2.A~.-DN, NTSPIu =AL- (---4 ) VALT + CL2 + DL.Rdom 2 + PMA 2 + PEA2 + ORE 2 + mR2 ) - RAVHias - DLBas (I 6 4 5 )( 1 .0 2 + 1.02 + 0.32812 + 02 +

_19.3 0.022 + 02) -0 0.0386 NTSPIu2 NTSPIU = 19.3 -1.156 NTSPIu =18.14 minutes 6.5.3 Licensee Event Report (LER) Avoidance Evaluation The purpose of the LER Avoidance Evaluation is to assure that there is sufficient margin provided between the AV and the NTSP to reasonably avoid violations of the AV. Any Z value greater than 1.29 provides sufficient margin between the NTSP and the AV. Therefore, NTSP 2 is calculated to provide upper and lower bounds for the NTSP based on LER avoidance criteria.

Sigma+(LER) = +(-)(VALN2 + CL2 + DL.Radom2 ) + DL.Bias 2

Sigma(LER)= +(2)(01.193 2 +1.02 +0.32812 )+0.0386 2

Sigma+ (LER) = +0.834 NTSP2u = AV - (Z x Sigma+ (LER))

NTSP2u = 18.0 -(1.29 x 0.834)

NTSP2U = 16.92 Therefore, an NTSP 2 < 16.92, will result in a Z greater than 1.29 and provide sufficient margin between the NTSP and the Allowable Value.

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 11 of 14 6.5.4 Selection of Operating Setpoint TS = NTSP 2U - ALT TS = 16.92 - 1.0 TS = 15.92 The setpoint will be rounded down to 15 minutes for added conservatism.

6.5.5 Establishing As-Found Tolerance (AFT)

An As-Found Tolerance is calculated to provide suggested limits for use during the surveillance testing:

AFT = +3 VA + DL.Random2 + DTE2 + DLBia 2

AFT=+/--3 V1.0' +0.3281' +02 +0.0386 2

AFT =-1.54 minutes, + 1.61 minutes These As Found tolerances produce As Found limits as follows]

AF = +TS + AFT AF = 15-1.54 to 15+1.61 AF = 13.46 minutes to 16.61 minutes A review of As-Found data (Input 4.4) shows that these relays have historically performed within the calculated AFT.

6.5.6 Required Limits Evaluation The purpose of a Required Limits Evaluation is to assure that the combination of errors present during calibration of each device in the channel is accounted for while allowing for the possibility that the devices may not be recalibrated. Since Leave Alone Zones are not used at MNGP, the devices are always verified or recalibrated to be within the As Left Zone. Therefore, a Required Limits Evaluation as discussed in the GE methodology is not applicable. Because the calibrated portion of this instrument loop consists only of the timers, the Loop As Found Tolerance is equal to the AFT from Section 6.5.5 above.

Loop AFT = AFT = -1.54 minutes and +1.61 minutes

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 12 of 14 As a result of Condition Report (CR) 02001013 (Reference 10.9), the As Found values are reviewed to verify that the As Found value is not outside the Technical Specification range. The As Found limits are not outside the Technical Specification range, and are therefore acceptable as computed in Section 6.5.5.

6.5.7 Spurious Trip Avoidance Evaluation Aspurious trip avoidance evaluation is performed to assure that there is a reasonable probability that spurious trips will not occur using the selected setpoint. Since the setpoint is evaluated against the high and low limits, a spurious trip avoidance evaluation is not applicable.

6.5.8 Elevation Correction None.

6.5.9 Determination of Action Setpoint The nominal setpoint of 15 minutes will be used.

7. Conclusions The results of the calculations are as follows:

Term Value (minutes) Section ALN: + 1.0 6.2.1.3 ALT: + 1.0 6.2.1.3 DL.Random: + 0.3281 6.2.1.4 DL.Bias: + 0.0386 6.2.1.4 ALT: + 1.0 6.2.1.5 CL: + 1.0 6.2.1.6 PEA: NA 6.3 PMA: NA 6.3 AV (calculated): < 18.0 6.5.1 NTSP 2 : 16.92 6.5.3

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 I Reactor Low Pressure Permissive Bypass Timer Page 13 of 14 Current Trip Setting: 20 + 1.0 4.13 Proposed Trip Setting: 15 + 1.0 6.5.1 AFT: -1.54, +1.61 6.5.5 AF Limits: > 13.46, < 16.61 6.5.5 Elevation Correction: NA 6.5.8

8. Future Needs

1. Revise procedure 0113-02 and supporting documentation as listed on the ADL of EC 20651 to reflect new setpoint.

9. Attachments Attachment A: Agastat Datasheet for EGP/EML/ETR Series Relays Attachment B: Excerpt from License Amendment 170

10. References 10.1 GE-NE-901-021-0492, DRF AOO-01932-1, Setpoint Calculation Guidelines for the Monticello Nuclear Generating Plant, October 1992.

10.2 General Electric Instrument Setpoint Methodology, NEDC-31336P-A, September 1996.

10.3 DBD B.03.01, Revision 4, Design Bases Document for Core Spray System.

10.4 DBD B.03.04, Revision 6, Design Bases Document for Reactor Heat Removal.

10.5 NX-7905-46-3, Revision 76, Schematic Diagram Residual Heat Removal System.

10.6 NX-7905-46-7, Revision 76, Schematic Diagram Residual Heat Removal System.

10.7 NEDC-32514P, Revision 1, October 1997, Monticello SAFER/GESTER-LOCA Loss-of-Coolant Accident Analysis.

10.8 Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to

Monticello Nuclear Generating Plant CA-03-036

Title:

Instrument Setpoint Calculation Revision 1 Reactor Low Pressure Permissive Bypass Timer Page 14 of 14 Accommodate a 24-Month Fuel Cycle.

10.9 Condition Report 02001013, Documentation of NRC Resident Question Regarding the Application of Tech Spec Deviations in As-Found Acceptance Criteria.

10.10 Amendment No. 62 to DPR-22, Dated 03/31/89, Reactor Vessel Level Instrumentation, ADS Logic Changes and S/RV Discharge Pipe Pressure Switch Setpoints.

CA-*0-, 0.3 *ev I

&IT-.A, AGA A 4/24/2002 Edition Nuclear Qualified Control Relays - Series EGP/EML/ETR SEISMIC AND RADIATION TESTED In order to satisfy the growing need for electrical to ANSI/IEEE C37.98 (formerly IEEE Standard control components suitable for class 1Eservice 501-1978, Standard for Seismic Testing of in nuclear power generating stations, AGASTAP Relays).

control relays have been tested for these The design of Series EGP, EML and ETR control applications. Series EGP, EML and ETR have relays has evolved over 20 years of continual use demonstrated compliance with the requirements in a wide range of industrial applications. Power of IEEE Standards 323-1974 (Standard for Relay, Magnetic Latch and Timing Relay versions qualifying Class 1E Equipment for Nuclear Power are available for use with a choice of coil Generating Stations) and IEEE Standard 344-1975 voltages, as well as an internal fixed or adjustable (Seismic Qualification for Nuclear Power potentiometer in the Series ETR time delay Generating Stations), Testing was also referenced version.

TEST PROCEDURE Test Procedure Seismic Aging voltage for AC units, and 80 and 120 percent of AGASTAT control relay Series EGP, EML and Sufficient interactions were performed at levels rated voltage for DC units, with temperatures ETR were tested in accordance with the require- less than the fragility levels of the devices in ranging from 40°F to 172°F at 95 percent ments of IEEE STD. 323-1974 (Standard for order to satisfy the seismic aging requirements relative humidity.

Qualifying Class 1E Equipment for Nuclear Power of IEEE STD 323-1974 and IEEE STO 344-1975. Baseline Performance Generating Stations), IEEE STO. 344-1975 Seismic Qualification In addition to aging tests, a series of baseline (Seismic Qualification for Nuclear Power Artificially aged relays were subjected to simulated tests were conducted before, and immediately Generating Stations) and referenced to ANSI/IEEE seismic vibration, which verified the ability of the after each aging sequence, in the following areas:

C37.98 (formerly IEEE Standard 501-1978, individual device to perform its required function Pull-in Voltage Standard for Seismic Testing of Relays). The before, during and/or following design basis Drop-out Voltage relays were tested according to parameters earthquakes. Relays were tested Inthe non- Dielectric Strength at 1650V 60Hz which, in practice, should encompass the operating, operating and transitional modes. Insulation Resistance majority of applications. Documented data applies Operate Time (milliseconds) to relays which were mounted on rigid test Hostile Environment Since the relays are Intended for use in auxiliary Recycle Time (milliseconds) fixtures. The following descriptions of the tests Time Delay (seconds) Series ETR performed are presented in their actual sequence. and control buildings, and not in the reactor containment areas, a hostile environment test Repeatability (percent) f only Radiation Aging was performed in place of the Loss of Coolant Contact Bounce Relays were subjected to a radiation dosage of Accident (LOCA) test. Relays were subjected to (milliseconds at 28VDC, 1 amp.)

2.0 X 101 Rads, which is considered to exceed combinalion extreme temperature/humidify plus Contact Resistance adverse plant operating requirements for such under/over voltage testing to prove their ability (milliohms at 28VDC, 1 amp.)

areas as auxiliary and control buildings. to function under adverse conditions even after Cycling with Load Aging having undergone all the previous aging Data was measured and recorded and used for The radiated units were then subjected to simulation and seismic testing. The devices comparison throughout the qualification test 27,500 operations at accelerated rate, with one were operated at minimum and maximum program In order to detect any degradation of set of contacts loaded to 120VAC, 60Hz at 10 voltage extremes: 85 and 120 percent of rated performance.

amps; or 125VD0C at 1 amp, and the number of mechanical operations exceeding those POLLCALE00CC SPEOTOCM (aPal) MWOWETCOTO%

1Wm =oo C .

experienced In actual service.

PING 5%

Temperature Aging This test subjected the relays to a temperature of 1OOC for 42 days, with performance measured before and after thermal stress.

in-TheSRS shape (at 5 percent damping), Is definedby fourpoints: C { 1IEE C I.IIf point A = 1.0 Hzand an accelerationequalto 25 percent ofthe ZeroPeriodAcceleration point D = 4.0 Hzand 250 percent of the ZPA pointE - 16.0 Hzand 250 percent ofthe ZPA (ZPA) i 11{1 I Ii pointG - 33.0 Hzand a levelequalto the ZPA SPECIMEN 13,15 & 16(EGPSERIES)

RELAY STATE: NON-OPERATE MODE)DE-ENER.) 1--

TESTRUNNO.318, 319,(205-206), (198-199)

AXIS(H+ V):

COMPOSITE OFFPN-,SSIV,FUN+ .707 DUETO45' INCLINATION OFTESTMACHINE.

Figure 1.Model EGP,Response Sectrnm, Non-Operate Mode Additional Seismic Response Curves are available an request.

.t- I RelayState: Non-Operate Modetfe-heer.) F L]q,,',c 100 loco TestRun No.318, 319, (205-206). (198-199) tqca/ Electronics Specifications subject to change Technical Support Center 1-800-522-6752 Dimensions are for reference only. 1 www.tycoelectronics.com

CA-O&4a4' PtV)I D%TV A.

Nuclear Qualified Control Relays OPERATION 0= == t~ =s __1t~ =_ ý,b ~ ý tI=n=1T r___n~

Series EGP Series ETR Power Relay Time Delay Relay Applying a continuous voltage to the coil (81- (Delay on Energization)

84) energizes the coil and instantaneously Applying a continuous voltage to the Input transfers the switch, breaking the normally terminals (31-84) starts a time delay lasting for closed contacts (M1-R1, M2-R2, M3-R3, M4- the preset time period. During this period the R4) and making the normally open contacts normally closed contacts (Four M-R sets)

(M1-T1, M2-T2, M3-T3, M4-T4). The contacts remain closed. At the end of the delay period, remain inthis transferred position until the coil the normally closed contacts break and the is deenergized, at which time the switch normally open contacts (Four M-T sets) make.

instantaneously returns the contacts to their The contacts remain inthis position until the original position. relay Is deenergized, at which time the contacts instantaneously return to their normal position.

Continuous Duty Wiring Deenergizing the relay, either during or after the Since the double wound coil does not have a delay period will recycle the unit within .075 continuous duty rating, voltage pulses to the second. Itwill then provide a full delay period coils should not exceed a ratio of 40% on, to upon reenergization, regardless of how often 60% off, with maximum power-on periods not the voltage is Interrupted before the unit has to exceed 10 minutes. been permitted to "time-out" to Its full delay INPUT setting.

Ifcontinuous energizing only is available, a resistor/capacitor network should be connected as shown below. Inthis case the shortest time between two operations must not be less than 5 seconds.

The relay will always assume the energized Series EML Magnetic Latch position in the event of both windings being energized simultaneously.

It is advisable not to put another load in parallel with the windings of the ML relay.

E-INPUTA Application of a voltage to the latching input (B1-84) will cause the relay to latch In (Make MLSeries Relay for DCoperation with a the N.O. Contacts, break the N.C. Contacts). resistor/capacitor network When this voltage is removed, the relay will remain inthis "Latched" condition. Application of a voltage to the un-latching input (83-14) will cause the relay to dropout (Break the N.O.

Contacts, make the N.C. Contacts). When this PRESET TIME DELAY voltage is removed, the relay will remain inthis "Unlatched" condition.

LATCHINPUT "*] ENERGIZED INPUT F L ENERGIZED DEENERGIZED 1-114 CLOSED OIDEENERGIZED N.C.CONTACTS L.-- OPEN (FOUR M-RSETS) ' LOPEN UNLATCH INPUT I ENERGIZED I CLOSED 113-84 I-* DEENERGIZED OPEN N.C.CONTACTS CLOSED (FOUR M-TSETS)

N.C.CON'TACTS CLOSED (FOURM-RSETS)IL

• J OPEN R-C Values NO. CONTACTS CLOSED (FOURM-TSETS) Nominal R C OPEN Voltage OHMS VDC k5% Wails UF VDC Wiring Diagram (Wiring and Connections)

The ML relay has three terminals for the 12 62 2 5000 15 windings: latching winding between terminals 24 240 2 2000 50 B1 and 84, un-latching winding between terminals B3 and B4. 48 1000 2 .500 100 The ML Relay is not symmetrical due to its 125 6200 2 150 150 three coil connections The relays are normally delivered polarized so that terminal B4 carries the negative voltage.

To reverse the polarity, a deenergize/energize cycle should be carried out using a voltage 50%

greater than the normal rating.

tqLo/ Electronics Specifications subject to change Technical Support Center 1-800-522-6752 Dimensions are for reference only. www.tycoelectronics.com

C:-o*3ts Rev A%,rr P,.

AG r6QA l Nuclear Qualified Control Relays SPECIFICATIONS Contact Ratings - The date of manufacture can be found in the first Series EGP/EML/ETR four (4) digits of the serial number on the nameplate Contact Capacity InAmperes (Resistive)

First two digits indicate the XX XX Contact Min. 1,000,000 year.

Voltage Operations 24 vdc 10.0 amps Second two digits Indicate the 125 vdc 1.0 amp week.

120 vac, 60 Hz 10.0 amps 240 vac, 60 Hz 7.5 amps Example In the date code "7814" below:

"78" indicates the year 1978; Contact Ratings, UL - Series EGP/EML Only "14" Indicates the 14th week Contact ratings as listed under the Underwriters (or April 3 through april 7).

Laboratory Component Recognition Program.

(Two poles per load): Model 1/3 Horsepower, 120 vac 10 amps, General Purpose, 240 vac Colt 125 VDC 120 vdc, 1.0 amp Serial 78140028 Mechanical Life - Series EGP/EML/ETR 25,000 mechanical operations Approximate Weight - Series EGP/EML/ETR Note 1 lb. Tyco Electronics Corporation does not recommend the use of Its products Inthe containment areas of Nuclear Power Transient Protection - Series ETR Only Generating Stations.

A 1500 volt transient of less than 100 microseconds, or 1000 volts of less than 1 millisecond will not affect timing accuracy.

Timing Adjustment - Series ETR Only Internal Fixed Internal Potentiometer Time Ranges - Series ETR Only

.15 to 3 Sec. 4 to 120 Sec.

.55 to 15 Sec. 10 to 300 Sec.

1 to 30 Sec. 2 to 60 Min.

2 to 60 Sec. 1 to 30 Min.

Repeat Accuracy - Series ETR Only The repeat accuracy deviation (AR)of a time-delay relay is a measure of the maximum deviation In the time-delay that will be experienced in five successive operations at any particular time setting of the relay and over the operating voltage and temperature range specified. Repeat accuracy is obtained from the following formula:

Replacement Schedule - Series Aý 100 (T, - Ta)

EGP/EML/ETR S(T+ Tz)

The qualified life of these relays is Where -

25,000 electrical operations or 10 years T" = Maximum Time Delay.

from the date of manufacture, whichever T2= Minimum Time Delay.

occurs first.

tqca / Electronics Specileations subject to change Technical Support Center 1-800-522-6752 Dimensions are for reference only. 3 www.tycoelectronlcs.com

CA 0~3p4~'~v I NT-rA.v Nuclear Qualified Control Relays OPERATING CHARACTERISTICS Environmental Candilons (Qualified Life)- Series EGP/EML/ETR Parameter Min, Normal Max.

Temperature (°F) 40 70-104 156 Humidity (R.H.%) 10 40-60 95 Pressure - Atmospheric -

Radiation (rads) - 2.0 x 10' (Gamma)

Operating Conditions, Normal Environment - Series EGP/EML/ETR Normal Operating Specifications With DC Calls With ACCoils EGP EML ETR EGP ETA Coil Operating Voltage, Nominal (rated)* As Spec. As Spec. As Spec. As Spec. As Spec.

Puel-in (% of rated value) 80% Min. 85% Min. 80% Min. 85% Min, 85% Min.

Drop-out (% of rated value) 5-45% 85% Min. 5-45% 5-45% 5-50%

Continuous (% of rated value) 110% Max. N/A 110% Max. 110% Max. 110% Max.

Power (Watts at rated value)

Pull-in 6 Apprx. 15 Apprx. 6 Apprx. 6 Apprx. 6 Apprx.

Drop-out N/A 13 Apprx. N/A N/A N/A Relay Operate time 30 ms Max. 25 ma Max, N/A 35 ms Max. N/A With min.

latch pulse of 30 ma.

Relay Release (Recycle) Time 25 ms Max. 20 ms Max. 75 ms Max. 85 ms Max. 75 ms Max.

With min.

latch pulse of 30 ms.

Contact Ratings, Continuous Resistive at 125 vdc 1.0 amp. 1.0 amp. 1.0 amp. 1.0 amp. 1.0 amp.

Resistive at 120 vac, 60 Hz 10.0 amp. 10.0 amp. 10.0 amp. 10.0 amp. 10.0 amp.

Insulation Resistance (In megohms at 500 vdc) 500 Min. 500 Min. 500 Min. 500 Min. 500 Min.

Dielectric (vrms, 60 Hz)

Between Terminals and Ground 1,500 1,500 1,500 1,500 1,500 Between Non-connected Terminals 1,500 1,500 1,500 1,500 1,500 Repeat Accuracy N/A N/A *5% N/A +/-5%

Operating Conditions, Abnormal Environment - Series EGP/EML Adverse Operating Spectlieations Normal OB'A" DO"B" DB"C' B D010 Temperature (°F)70-104 40 120 145 156 Humidity (R.H.%) 40-60 10-95 10-95 10-95 10-95 Coil Operating Voltage (% of rated)*

AC(Series EGPonly)85-110 85-110 85-110 85-110 85-110 DC(Series EGP only)80-110 80-110 80-110 80-110 80-110 DC(Series EMLonly)85-110 85-110 85-110 85-110 85-110 Relay Operate Time (ms)

AC(Series EGP only) 35 Max. 35 Max. 35 Max. 35 Max. 35 Max.

DC(Series EGP,Series EML) 30 Max. 25 Max. 37 Max, 40 Max. 40 Max.

Operating Condltions, Abnormal Environment - Series ETR Adverse Operating Specilications With DCCells With ACCoals Coil Operating Voltage (rated)* As Spec. As Spec.

Pull-In (%of rated value) 80%/6 Min. 85% Min.

Continuous (% of rated value) 110% Max. 110% Max.

Drop-out (% of rated value) 5-45% 5-50%

Power (Watts at rated value) 6 Apprx. 6 Apprx.

Relay Release (Recycle) Time 75 ms Max. 75 ms Max.

Contact Ratings, Continuous Resistive at 125 vdc 1.0 amp. 1.0 amp.

Resistive at 120 vac, 60 Hz 10.0 amp. 10.0 amp.

Repeat Accuracy +/-10% 110%

• Allcolls may be operated on Intermittent duty cycles at voltages 10% above listed maximums (Intermittent Duty = Maximum 50% duty cycle and 30 minutes "ON" time.)

tqca/ Electronics Specifications subject to change Technical Support Center 1-800-522-6752 0imensions are for reterence only. 4 www.tycoelectronlcs.com

i\rrA.

Nuclear Qualified Control Relays DIMENSIONS AND MOUNTING Series EGP, EMLand ETRAGASTATO control relays must be mounted Inthe horizontal position;,performance specifications of these units are valid only when they are mounted as Indicated Ineither ofthe above drawings.

tqca/ Electronics Spectilcatilons subject to change Technical Support Center 1-800-522-6752 Dimensions are for reference only. 5 www.tycoelectronncs.com

AGASTA Nuclear Qualified Control Relays ORDERING INFORMATION Catalog Number Code - Series EGP and EML Ii I I' Nuclear AGASTAT Coil Configuration Salety Control Voltage Code*

Related Relay Model Code Code Code Code 004 E GP - Power A- 12 VDC Relay B-24 VDC ML - Magnetic C-48VDC Latch DC - 125 VDC L E-110 VDC F - 250 VDC (Series EGP Only)

K G- 24 VAC 60 Hz (Series EGP Only)

H- 48 VAC 60 Hz (Series EGP Only)

AC I-120 VAC 60 Hz (Series EGP Only)

L J - 220 VAC60 Hz (Series EGP Only)

Conllguralian Code The Configuration Code isa suffix to the Model Number which provides a means of Identification. When a significant product change Isintroduced, the Configuration code and specification sheets will be revised.

Ii Nuclear AGASTA Operating Timing Time Configuration Safety Control Voltage Adjustment Range Code Related Relay Model Code Code Code Code Code Code DCDOB-- 24 VDC 1- Internal A-. 15 to 3 sec. 004 E TR14-Time 125 VDC Fixed B- .55 to 15 sec.

Delay 3 - Internal C- 1 to 30 sec.

Relay AC 1- 120 VAC 60Hz . Potentiometer 0 - 2 to 60 sec.

t._

(Delay E- 4 to 120 sec.

on G- 10 to 300 sec.

Pull-in) I - 2 to 60 min.

N- 1 to 30 min.

Conliguratlon Code The Configuration Code is a suffix to the Model Number which provides a means of Identification. When a significant product change IsIntroduced, the Configuration code and specification sheets will be revised.

tq / Electronics Specifications subject to change Technical Support Center 1-800-522-6752 Dimensions are for reference only. www.tycoelectronics.com

0\-03-03 G. Jo \t Avrr. 'A.

AGyCas Relay Classifications Control Code Summary CONFIGURATION CONTROL Product Code - 001 Code -002 Code -003 Code-004 EGP Contains all materials present In Nov. 1981 - Material change to Dec. 1987 - Material change on Dec. 1995 - Material change on original qualification testing. coil wrapping tape and lead wire leaf spring from nickel copper bobbin from Nylon Zytel 101 to insulation to improve thermal to beryllium copper. Rynite FR530. Material change life. on base from Melamine Phenolic to Grilon PMV-5HVO.

EML Contains all materials present in Nov. 1981 - Material change to Dec. 1987 - Material change on Dec. 1995 - Material change on original qualification testing. coil wrapping tape and lead wire leaf spring from nickel copper bobbin from Nylon Zytel 101 to insulation to Improve thermal to beryllium copper. Rynite FR530. Material change life. on base from Melamine Phenolic to Grilon PMV-SHVO.

ETR Contains all materials present in Nov. 1981 - Material change to Dec. 1987 - Material change on Dec. 1995 - Material change on original qualification testing. coil wrapping tape and lead wire leaf spring from nickel copper bobbin from Nylon Zytel 101 to insulation to Improve thermal to beryllium copper. Rynite FR530. Material change life. on base from Melamine Phenolic to Grilon PMV-5HVO.

ECROO01 Contains all materials present in June 1989 - Material change original qualification testing. from Noryl N-225 std. black to Noryl SE-1-701AA black.

ECROO02 Contains all materials present in original qualification testing.

June 1989 - Material change from Noryl N-225 std. black to ECROO95 Contains all materials present in Noryl SE-1-701AA black.

original qualification testing.

ECRO133 Contains all materials present in original qualification testing.

ECRO155 Contains all materials present in original qualification testing.

I a Configuration Code: The Configuration code is a suffix to the Model Number which provides a means of identification. When a significant product change Is introduced, the Configuration code and specification sheets will be revised. (001, 002, 003, 004, etc.).

tqca / Electronics Specifications subject to change Technical Support Center 1-800-522-6752 Diensions are for reference only. 7 www.tycoelectronics.com

CA 05 Rcv I A'-r-. B.

nR UNITED STATES AQ NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 7, 2012 Mr. Mark A. Schimmel Site Vice President Monticello Nuclear Generating Plant Northern States Power Company - Minnesota 2807 West County Road 75 Monticello, MN 55362-9637

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - ISSUANCE OF AMENDMENT REGARDING THE AUTOMATIC DEPRESSURIZATION SYSTEM BYPASS TIMER (TAC NO. ME8345)

Dear Schimmel:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 170 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant.

The amendment consists of changes to the technical specifications (TSs) in response t6 your application dated April 5, 2012.

The amendment revises TSs to eliminate the lower allowable value limit of ">18 minutes" for Functions I.e and 2.e, "Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive)," in Table 3.3.5.1-1, "Emergency Core Cooling System Instrumentation."

Please note that the NRC staff declined to issue this amendment by the licensee's requested issuance date of June 6, 2012; the application did not provide any reason for shortening the regulatory 60-day notice period during which interested parties may petition for a hearing.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly FederalRegister notice.

Sincerely, SS ior Project Manager Plant Licensing Branch I1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263

Enclosures:

1. Amendment No. 170 to DPR-22

2. Safety Evaluation cc w/encls: Distribution via ListServ

L-MT-13-019 ENCLOSURE 5 GENERAL ELECTRIC- HITACHI AFFIDAVIT FOR WITHHOLDING PROPRIETARY INFORMATION 3 pages follow

GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, James F. Harrison, state as follows:

(1) I am the Vice President Fuel Licensing of GE-Hitachi Nuclear Energy Americas LLC (GEH), and have been delegated the function of reviewing the information described in paragraph (2) that is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in GEH proprietary report NEDC 33800P, "Monticello Nuclear Generating Plant Automatic Depressurization System Bypass Timer Extended Power Uprate," Revision 0, dated January 2013. GEH proprietary information in NEDC-33800P is identified by a dark red dotted underline inside double square brackets, ((Th.ibs sentence is an examp.le..13).)). Figure and large equation objects containing GEH proprietary information are identified with double square brackets before and after the object. In each case, the superscript notation (3)refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 U.S.C. Sec. 552(b)(4), and the Trade Secrets Act, 18 U.S.C.

Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 as decided in Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F.2d 871 (D.C. Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F.2d 1280 (D.C. Cir. 1983).

(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:

a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over GEH or other companies.

b. Information that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.

C. Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, that may include potential products of GEH.

d. Information that discloses trade secret or potentially patentable subject matter for which it may be desirable to obtain patent protection.

NEDC-33800P, Revision 0 Affidavit Page I of 3

(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to the NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary or confidentiality agreements that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure are as set forth in the following paragraphs (6) and (7).

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH. Access to such documents within GEH is limited to a "need to know" basis.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary and/or confidentiality agreements.

(8) The information identified in paragraph (2), above, is classified as proprietary because it contains detailed results of an analysis performed by GEH to support the Monticello Extended Power Uprate (EPU) license application. This analysis is part of the GEH EPU methodology. Development of the EPU methodology and supporting analysis, techniques, and information and their application for the design, modification, and processes were achieved at a significant cost GEH.

The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GEH asset.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.

The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.

NEDC-33800P, Revision 0 Affidavit Page 2 of 3

The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.

Executed on this 14 th day of January 2013.

James F. Harrison Vice President Fuel Licensing GE-Hitachi Nuclear Energy Americas LLC 3901 Castle Hayne Rd Wilmington, NC 28401 james.harrison@ge.com NEDC-33800P, Revision 0 Affidavit Page 3 of 3