ML13323A552

Attachment 3 to GNRO-2013/00088, JC-Q1B21-N681-1 Rev. 1 Reactor Pressure Vessel Level One Setpoint Calculation

ML13323A552
Person / Time
Site:	Grand Gulf
Issue date:	10/14/2013
From:	Entergy Operations
To:	Office of Nuclear Reactor Regulation
References
GNRO-2013/00088, TAC ME9764 JC-Q1B21-N681-1, Rev 1
Download: ML13323A552 (50)

Text

Attachment 3 to GNRO-2013/00088 JC-QIB21-N681-1 Rev. I "Reactor Pressure Vessel Level One Setpoint Calculation" El ANO-1 [I ANO-2 0 GGNS [ IP-2 [I IP-3 0 Pu'[Q JAF EJPNPS C3 RBS Q] W3 D NP-GGNS-3 NP-RBS-3 CALCULATION ) EC # 39554 (2)Page I of 49 COVER PAGE (3) Design Basis Caic. Z YES E" NO (4) [ CALCULATION El EC Markup s Calculation No: JC-QIB21-N681-1

.61 Revision:

001 7 Title: Level 1 Setpoint Calculation ) Editorial[:_ YES IZNO) System(s):

B21 (10) Review Org (Department):

NPE I&C (11) Safty Class: (12) Component/Equipment/Structure Type/Number:

[ Safety / Quality Related IB21NO91A, B, E, F 1B21NO81A, B, C, D-Augmented Quality Program NA entSafedQaity P m 1B21N691A, B, E, F 1B21N681A, B, C, D Li Non-Safety Related___________

___________

(13) Document Type: J05.02 (4) Keywords (Descriptionfropical Codes): N/A REVIEWS (ts Nine/Signature/Date

('6) Name/Signature/Date i Name/Signature/Date Robin Smith 1W 4 -Mary Cgffaro /?fJdA o _______Responsible Engineer Z Design Verifier Supervisor/Approval 0l Reviewer__ Comments Attached E] Comments Attached CALCULATION SHEET-ENTERGY SHEET 2 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 zRevisiou Riecord: of R e5vision 0 Initial Issue EC-39554.

Revised to incorporate GEXI2000-00134, GIN 1996-02302, CR-GGN-2007-04245 and the transmitter drift calculation results from JC-Q1 111-09017.

1 Revised density error calculation.

Incorporated tap location uncertainty, Rev 7 to E100.0 and field compensation for static pressure.

Revised reactor trip condition discussions.

Added TSTF-493 Section 8.0.

A CALCULATION SHEET~--ENTERGY SHEET 3 OF 49 CALCULATION NO. JC-0IB21-N681-1 REV. 1 CALCULATION CALCULATION NO: JC-Q1B21-N681-1 Rev 1 REFERENCE SHEET I. EC MARKUP's INCORPORATED:

None II. RELATIONSHIPS:

Sht Rev Input Output Impact Tracking No.Doc Doc Y/N 1. JS09 0 001 0] E N 2. J1281L 003A 000 10 E N 3. J1281L 003B 000 0 El N 4. J1281L 003C 000 0l E N 5. J1281L 003D 000 l El N 6. J1281L 024A 001 E0 0 N 7. J1281L 024B 001 0 El N 8. J1281L 024E 000 E0 E N 9. J1281L 024F 000 10 E N 10. M1077B 0 034 0 El N 11. 184C4571 001 009 0 El N 12. GEXI2000-00134

-- 0 0 El N 13. 169C8392 002 008 0 El N 14. NEDC31336

-- 0 0 El N 15. CR-GGN-2007-04245 0 0 El N 16. PERR91-6068 1 0 El N 17. GIN96-02302 0 0 El N 18. GEXO2012-00384

-- 000 0 El N 19. J1601A 0 003 0 El N 20. 06-IC-1B21-R-2005

-- 105 E0 0 Y CR-GGN-2012-09971 CA#12 21. 06-IC-IB21-R-0008 107 0 El Y CR-GGN-2012-09971 CA#12 22.06-IC-1B21-Q-2004 104 0 El Y CR-GGN-2012-TCN002 09971 CA#12 23. 06-IC-1B21-Q-1007

-- 105 0 El Y CR-GGN-2012-09971 CA#12 24. E100.0 0 007 0 El N 25.460000047 0 300 0 El N 26. 460001972 0 300 0 El N 27. JI601B 0 003 0 El N 28. 164C5150 001 018 0 El N a CALCULATION SHEET-ENTERGY SHEET 4 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 29. 368X543BA 0 044 0 0 N 30. 368X544BA 0 025 0 0 N 31. 368X558BA 0 024 0 0 N 32. J1507A 0 001 0 0 N 33. J1507B 0 001 0 0 N 34. J1507C 0 001 0 0 N 35. J1507D 0 001 0 0 N 36. J0400 0 018 0 0 N 37. J0401 0 014 0 0 N 38. A0552 0 018 0 0 N 39. A0553 0 015 0 0 N 40. A0554 0 011 .10 0 N 41. 368X559BA 0 039 0 0 N 42. 865E516 002 008 0] 0 N 43. 865E517 002 015 0 0 N 44. 865E520 002 008 0 0 N 45. 865E521 002 007 0 0l N 46. 865E522 002 006 0 0f N 47. 865E523 002 006 0 0 N 48. 460000944 0 300 0] E0 N 49.22A3856AA 0 012 0 0 N 50. JC-Ql1111-09017 0 000 0 0 N 51. GGNS-NE-09-00018

-- 002 0 0 N 52. EC-0000044848 000 000 0 0 N 53. EIRR85-10233

-- 000 0 0 N 54. GGNS-NE-09-00001

-- 001 0 0 N 55. GGNS-SA-09-00001

-- 000 0 0 N 56. GEXO2009-00106

-- 000 0 0 N III. CROSS

REFERENCES:

1. Asset Suite EDB 2. GGNS UFSAR, Figure 15.2-10 3. GGNS UFSAR, Figure 6.2.7 4. GGNS UFSAR, Figure 6.2.-14 5. GGNS Technical Specifications, Table 3.3.5.1-1 6. GGNS Technical Specifications, Table 3.3.6.1-1 7. GGNS Technical Specifications, Table 3.3.6.3-1 8. GGNS Technical Specifications, Table 3.3.6.4-1 9. GGNS Technical Specifications, Table TR3.3.5. 1-1 10. GGNS Technical Specifications, Table TR3.3.6.1-1 a CALCULATION SHEET-ENTERGY SHEET 5 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. I 11. GGNS Technical Specifications, Table TR3.3.6.3-1

12. GGNS Technical Specifications, Table TR3.3.6.4-1

13. GGNS Technical Specifications, Figure B3.3.1.1-1

14. ASME Steam Tables, 6'h Edition 15. GGNS Technical Specification Section 3.3.6.5.3 IV. SOFTWARE USED: Title: N/A Version/Release:

Disk/CD No.V. DISK/CDS INCLUDED: Title: Version/Release Disk/CD No.VI. OTHER CHANGES: Related references no longer used: M5.8.003, ES 19, C196.0, MS02, JS08, M1020, 762E543, J0187PD, 204B7660, 22A4622, M1077A, J1247 Shts 1,2,5,8, El 160 Sh 57, El 173 Sh 26, El 181 Sh 64, E1182 Sh 24, J1271 Sh 44, J1279 Sh 1,2, J1281 Shts 10,1 1A, 1B,13,C,1 1D,14,18,19,20,21,22,23,39,40, (all previously referenced FSK drawings).

CALCULATION SHEET ENTERGY SHEET 6 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 TABLE OF CONTENTS COVER SHEET RECORD OF REVISION CALCULATION REFERENCE SHEET TABLE OF CONTENTS SHEET 1 2 3 6 SECTION 1.0 2.0 3.0 4.0 5.0 PURPOSE DESIGN REQUIREMENTS REFERENCES GIVEN ASSUMPTIONS 7 7 8 11 15 20 22 31 33 6.0 METHODOLOGY

7.0 CALCULATION

8.0 TSTF CALCULATIONS

9.0 CONCLUSION

APPENDICES N/A ATTACHMENTS 1 Design Verification Form 2 Owner's Review Comments (5 sheets)(11 sheets)

• h CALCULATION SHEET-i-O ENTERGY SHEET 7 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 1.0 PURPOSE The purpose of this calculation is to determine the allowable value and the nominal trip setpoint for all Reactor Vessel Level 1 safety-related, Technical Specification trip loops.The values generated by this calculation are in accordance with JS09 (Ref. 3.1.1) and NEDC31336 (Ref 3.1.14).2.0 DESIGN REQUIREMENTS There are eight loops that provide Level 1 trip functions.

All eight loops are wide range loops with a range from -160 to +60 inches (Refs. 3.1.19, 3.1.27). The level I reactor water level loops perform the following trips (Refs. 3.2.6-3.2.9):

1) LPCS/LPCI Initiation

2) ADS Initiation

3) MSIV Isolation 4) Primary Containment Isolation 5) Containment Spray Actuation 6) Suppression Pool Makeup Actuation The bounding DBE for this calculation will be a DBA Large Break, Intermediate or Small Break LOCA. Elevated drywell temperatures are considered (Assumption 5.21).These instruments are classified as QF I (Ref. 3.2.1). Therefore, they are required to operate after seismic conditions.

Per Reference 3.1.1, seismic effects are not required to be considered for setpoint loops because the reactor will be shutdown following a seismic event. Therefore seismic effects will not be considered for the subject loops.The analytical limit for the level 1 trip is -154.7 inches (Ref. 3.1.40). The Technical Specification Allowable Value is > -152.5 inches (Refs. 3.2.6-3.2.9) and the Technical Specification Trip Setpoint is > -150.3 inches (Refs. 3.2.10-3.2.13).

Reactor Vessel Level 1 Setpoint should be high enough to allow time for the low pressure core spray injection systems to activate and provide adequate core cooling in the event of a large break LOCA, but low enough that the decrease in level resulting from a reactor scram or other operational transients will not cause an unnecessary initiation.

For ADS, if HPCS & RCIC cannot maintain water level and other necessary permissives are present, the Level 1 initiation signal ensures that ADS can depressurize the reactor in time to allow LPCI & LPCS to limit fuel cladding temperature.

A CALCULATION SHEET ENTERGY SHEET 8 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. 1

3.0 REFERENCES

3.1 Relationships

3.1.1 Standard

No. GGNS-JS-09, Methodology for the Generation of Instrument Loop Uncertainty

& Setpoint Calculations 3.1.2 J1281L-003A, Loop Diagram 3.1.3 J1281L-003B, Loop Diagram 3.1.4 J1281L-003C, Loop Diagram 3.1.5 J1281L-003D, Loop Diagram 3.1.6 J1281L-024A, Loop Diagram 3.1.7 J1281L-024B, Loop Diagram 3.1.8 J1281L-024E, Loop Diagram 3.1.9 J 1281L-024F, Loop Diagram 3.1.10 M1077B, P&ID 3.1.11 184C4571, Sh 1, Power Supply PPD 3.1.12 GEXI2000-00134, Statistical Variation Associated With Published Performance Variable 3.1.13 169C8392, Sh. 2, PPD Rosemount 1152 Transmitters 3.1.14 NEDC-31336P-A, Class 3, September 1996, General Electric Instrument Setpoint Methodology 3.1.15 CR-GGN-2007-04245 3.1.16 PERR91-6068 3.1.17 GIN96-02302 3.1.18 Not Used 3.1.19 J1601A 3.1.20 06-IC- I B2 1 -R-2005, N08 1 A-D Loop Calibration Instruction 3.1.21 06-IC- I B2 I -R-0008, N09 1 A,B,E.F Loop Calibration Instruction 3.1.22 06-IC-i B21-Q-2004, N681A-D Loop Functional Test Instruction 3.1.23 06-IC- I B2 1-Q- 1007, N69 1 A,B,E,F Loop Functional Test Instruction 3.1.24 Standard GGNS-E-100.0, "Environmental Parameters for GGNS" 3.1.25 Vendor Manual 460000047, Rosemount Instruction Manual 4247-1, dated 7/76, Trip/Indicator 3.1.26 Vendor Manual 460001972, Rosemount 1153 Transmitters 3.1.27 J1601B fCALCULATION SHEET__~ ENTERGY SHEET 9 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 3.1.28 164C5150, Sh. 1, PPD Rosemount Trip Units 3.1.29 368X543BA, EDL P004 3.1.30 368X544BA, EDL P005 3.1.31 368X558BA, EDL P026 3.1.32 368X559BA, EDL P027 3.1.33 865E516-002, EDL 1H13-P618 3.1.34 865E517-002, EDL 1H13-P629 3.1.35 865E520-002, EDL 1H13-P691 3.1.36 865E521-002, EDL 1H13-P692 3.1.37 865E522-002, EDL IH13-P693 3.1.38 865E523-002, EDL 1H13-P694 3.1.39 Vendor Manual 460000944, Rosemount 1152 Transmitters 3.1.40 GE Design Specification Data Sheet 22A3856AA 3.1.41 JC-Q 1111-09017, Drift Calculation for Rosemount Range Codes 4-7 Differential Pressure Transmitters 3.1.42 J 1507A, Instrument Location (Panel 1 H22-P004)3.1.43 J1507B, Instrument Location (Panel 1H22-P026) 3.1.44 J1507C, Instrument Location (Panel 1H22-P005) 3.1.45 J 1 507D, Instrument Location (Panel 1 H22-P027)3.1.46 J0400, Panel Location ( 1H 13-P601, P618, P692, P694)3.1.47 J0401, Panel Location (1H13-P691, P6938, P629)3.1.48 A0552, Floor Plan 3.1.49 A0553, Floor Plan w/Control Room 3.1.50 A0554, Floor Plan w/UCS Room Nos.3.1.51 Not Used 3.1.52 GGNS-NE-09-00018 3.1.53 GEXO2012-00384, Small Break LOCA Timing For Low Pressure ECCS Permissive 3.1.54 EC 44848-000, Approval Of Short Term Containment Analysis For Small Break LOCA (GE Report 0000-0159-5977), Issuance Of Calculation To Determine Sensing Line Temperature Of Reactor Water Level Transmitters 3.1.55 EIRR85-10233 ahETEG CALCULATION SHEET---ENTERGY SHEET 10 OF 49 CALCULATION NO. JC-O 1 B21-N681-1 REV. 1 3.1.56 GGNS-NE-09-0000 1, GGNS EPU -Heat Balance 3.1.57 GGNS-SA-09-00001 3.1.58 GEXO2009-00106

3.2 Cross

References

3.2.1 Asset

Suite EDB 3.2.2 GGNS UFSAR Figure 15.2-10 3.2.3 GGNS UFSAR, Figure 6.2.7 3.2.4 Not Used 3.2.5 GGNS UFSAR Figure 6.2-14 3.2.6 GGNS Technical Specifications, Table 3.3.5.1-1 3.2.7 GGNS Technical Specifications, Table 3.3.6.1-1 3.2.8 GGNS Technical Specifications, Table 3.3.6.3-1 3.2.9 GGNS Technical Specifications, Table 3.3.6.4-1 3.2.10 GGNS Technical Specifications, Table TR3.3.5.1-1 3.2.11 GGNS Technical Specifications, Table TR3.3.6.1-1 3.2.12 GGNS Technical Specifications, Table TR3.3.6.3-1 3.2.13 GGNS Technical Specifications, Table TR3.3.6.4-1 3.2.14 GGNS Technical Specification Section 3.3.6.5.3 3.2.15 Not Used 3.2.16 GGNS Technical Specifications, Figure B3.3.1.1-1 3.2.17 Not Used 3.2.18 ASME Steam Tables, 6th Edition.

(~) CALCULATION SHEET-ENTERGY SHEET 11 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. 1 4.0 GIVEN 4.1 Instrument Loop Block Diagram Transmitter I B21-LT-N091A,B,E,F 1B21-LT-NO81A,B,C,D Trip Unit 1B21-LIS-N691A,B,E,F 1B21-LIS-N681A,B,C,D Power 1 E21 K702 IE12K704 1B21K613A,B,C,D P&ID Loop Diagram 3.1.10 3.1.2-3.1.9

4.2 Transmitter

Environment Description Tag Number Data 1 B21 -LT-N091A,B,E,F 1 B21-LT-N081A,B,C,D 1H22-P004, P005, P026, P027 1A311, 1A313 Reference Instrument Location: Panel Room 3.1.2-3.1.9 3.1.42-45, 48 I Environmental Conditions (worst case): Normal: Temperature Pressure Radiation (Gamma)Humidity DBE or Accident: Temperature Radiation Seismic Conditions:

Surveillance Intervals:

Zone N-068, N-069 60-95°F-I to -0.1 inwc 6.3E3 rads (40 yr TID)0.026 R/hr gamma 20-90% RH Zone A-016 101 0 F N/A 3.1.24 3.1.24 3.1.24 3.1.24 3.1.24 Assumption 5.21 Assumption 5.21 N/A Section 2.0 30 months Assumption

5.9 CALCULATION

SHEET ENTERGY SHEET 12 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 4.3 Trip Unit Environment Description Tag Number Instrument Location: Panel Room Environmental Conditions:

Normal: Temperature Pressure Radiation (Gamma)Humidity DBE or Accident: Surveillance Intervals Data 1 B21 -LIS-N691A,B,E,F 1 B21 -LIS-N681A,B,C,D Reference 1H 13-P618,629,691,692,693,694 3.1.2-3.1.9 0C504/703 3.1.46, 47, 49, 50 Zone N-028 69-90°F 0.1 to 1.0 inwc 1.8E2 rads (40 yr TID)0.5 millirads/hr dose rate 20-50% RH Same as Normal 3.1.24 3.1.24 3.1.24 3.1.24 3.1.24 3.1.24 115 days Assumption 5.9 4.4 Transmitter Vendor Data, Rosemount 1153DD5PC/1153DB5RC Description Tag Number Manufacturer Data 1B21-LT-N091A,B,E,F 1B21-LT-N081A,C Reference Rosemount 3.1.29, 3.1.30, 3.1.32 Model 1153DD5PC (N091A,B,E,F) 1153DB5RC (N081A,C)750 inwc-160 to +60 inches level 3.1.29, 3.1.32 3.1.29, 3.1.30 3.1.26 3.1.20, 3.1.21 URL Span Range-227.34 to -71.0 inwc-227.74 to -71.39 inwc-227.34 to -71.0 inwc-227.74 to -71.39 inwc-227.34 to -70.99 inwc-227.29 to -70.94 inwc Span 156.34 inwc 156.35 inwc 156.34 inwc 156.35 inwc 156.35 inwc 156.35 inwc Transmitter 1B21-LT-NO91A 1B21-LT-NO91B I B21-LT-N091E 1B21-LT-NO91F IB21-LT-NO81A 1B21-LT-NO81C Accuracy:+/- 0.25% span (3ay)Drift:+/- 1.218% span for 30 months with -0.0443% span bias 3.1.12, 3.1.26 3.1.41 ACALCULATION SHEET___- ENTERGY SHEET 13 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. I Power Supply: Temperature:

Humidity: Radiation:

Static Press (Zero): Static Press (Correction):

Static Press (Span): Seismic: Overpressure:

Output Range 4.5 Transmitter Vendor Data, Description Tag Number Manufacturer Model URL Span Range-227.74 to -71.39 inwc-228.907 to -72.552 inwc Accuracy: Drift: Power Supply: Temperature:

<0.005% span per volt (3a) 3.1.12, 3.1.26+/- (0.75% URL + 0.5% span)/100 0 F (3a) 3.1.26 3.1.12 Sealed unit -no effects 3.1.26 N/A Assumptions 5.6, 5.21+/- 0.2% URL / 1000 psi (3a) 3.1.12,3.1.26

+/- 0.5% Reading / 1000 psi (3y) 3.1.12, 3.1.26* 0.75% Reading / 1000 psi (3a) 3.1.12, 3.1.26+/- 0.5% URL for 7 g ZPA 3.1.26+ 1.0% URL for 2000 psi (3a) 3.1.12, 3.1.26 4-20 madc 3.1.26 Rosemount 1152DP5N22T0280PB Data Reference 1B21-LT-N08 IB,D Rosemount 3.1.31,3.1.32 1152DP5N22T0280PB 3.1.13,3.1.31,3.1.32 750 inwc 3.1.39-160 to +60 inches level 3.1.20 an Transmitter 156.35 inwc 1B21-LT-NO81B 156.335 inwc 1B21-LT-NO81D

+ 0.25% span (3a) 3.1.12, 3.1.39+/- 1.218% span for 30 months 3.1.41 with -0.0443% span bias<0.005% span per volt (3a) 3.1.39, 3.1.12+/- 5.00% Span/100F

(@ min span) (3a) 3.1.39 (0-125 inwc) 3.1.12 isa TEG CALCULATION SHEET---ENTERGY SHEET 14 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1+ 1.25% Spanl100F

(@ max span) (3a)(0-750 inwc)Humidity: Radiation:

Sealed unit -no effects N/A 3.1.39 Assumptions 5.6, 5.21 Static Press (Zero):+ 0.25% URL / 2000 psi (3a)3.1.12, 3.1.39 Static Press (Correction):

-1.0 +/- 0.25% Reading / 1000 psi (3y) 3.1.12, Assumption 5.14+0.81% Reading/ 1000 psi (3a) 3.1.12, Assumption 5.14 Static Press (Span): Seismic:+/- 0.25% URL for 3 g ZPA 3.1.39 Overpressure:

Output Range+/- 1.0% URL for 2000 psi (3a) 3.1.12, 3.1.39 4-20 madc 3.1.39 4.6 Trip Unit Vendor Data Description Tag Number Manufacturer Data Reference 1 B21-LIS-N691A,B,E,F 1 B21 -LIS-N681A,B,C,D Rosemount Model 510DU 3.1.28, 3.1.33-3.1.38 3.1.16, Assumption 5.20 3.1.25, Note 1, 3.1.14 Repeatability:

+/- 0.2% span (3a)Drift: N/A Assumption

5.7 Input

Range 4-20 madc 3.1.25 Note 1: Table 5 of reference 3.1.25 defines environmental conditions at the Trip Switch in terms of "operating condition" and "environment." Conditions in Zone N-028 are bounded by line 2 defined as "adverse operating conditions" and "normal environment" The corresponding line on Table 6 specifies repeatability under the defined conditions as+/-0.20%. This repeatability is valid for six months operation.

An allowance for power supply effects, temperature effects, humidity effects, drift and radiation effects are included in the repeatability.

,4.7 Power Supplies Power Supply Nominal 24.0 volts Assumption

5.3 Power

Supply Variations 23 -28 vdc Assumption 5.3 5.0 ASSUMPTIONS 5.1 All uncertainties given in vendor data specifications are assumed to be 2 sigma unless otherwise specified.

• 5.2 Per reference 3.1.1, the M&TE error is normally assumed to be equal to the reference accuracy of the transmitter.

Per references 3.1.20 and 3.1.21, a Fluke 45 and a pressure gauge are used to calibrate the transmitters, these instruments have a combined M&TE error of _< 10.041 ma. Converting the ma error to inwc: (0.040 ma)(156.35 inwc / 16 ma) = 0.40 inwc. The setting tolerance from references 3.1.20 and 3.1.21 is +/-0.04 ma, or +0.40 inwc. As the test equipment error (setting tolerance) is larger than the reference accuracy of the transmitter

(+/-0.27 inwc), +/-0.40 inwc will be assumed for the M&TE error.Per references 3.1.22 and 3.1.23, a Rosemount readout assembly is used to calibrate the Rosemount trip units. Per reference 3.1.25, the accuracy of the readout assembly is +/-0.0.1 ma,*which is equal to (0.01 ma)(156.35 inwc/16 ma) =+/-0.10 inwc (MTE 2) and the accuracy of the trip unit is +/-0.2% span = (2/3)*0.2%

(156.35 inwc) = +/-0.21 inwc. References 3.1.22 and 3.1.23 specify a setting tolerance of +/-0.03 ma = (0.03)(156.35/16)

= 0.30 inwc. The larger +/-0.30 inwc setting tolerance value will be assumed for the M&TE error.5.3 A maximum value of 28 vdc and minimum of 23 vdc will be assumed for power supply variation, as this is the value provided in PPD 184C4571 for the 24 vdc power supplies (Ref. 3.1.11). This results in an assumed voltage variation of +4,-1 vdc. Per reference 3.1.17, one of the loop power supplies was replaced with a Vicor model VI-N53-IM DC-DC converter that has a maximum variation of 0.55%, which is bounded by the original power supply variation.

For conservatism, +4 vdc will be used in this calculation.

5.4 The transmitters addressed in this calculation are powered by Rosemount trip units. The amount of fluctuation in the transmitter excitation voltage (caused by fluctuations in the supply voltage of the trip units) is not addressed in the trip unit vendor manuals. To be conservative, it will be assumed that the maximum fluctuation of the excitation voltage is equal to the maximum fluctuation of the trip unit power supply output.5.5 The specified overpressure effect of the Rosemount transmitters is for an.overpressurization above the URL but below 2000 psi (Refs. 3.1.26, 3.1.39). It is assumed the maximum differential pressure will not exceed the URL of 750 inwc and OVP will not apply.

ft CALCULATION SHEET~--ENTERGY SHEET 16 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. 1 5.6 The radiation drift effect (RD) of the transmitters is assumed to be zero as they are calibrated every 30 months (maximum).

Assumption 5.9.5.7 The accuracy of the Rosemount trip units (+/-0.2% span) is valid for six months (Ref. 3.1.25). The trip units are calibrated every 115 days (Assumption 5.9).Therefore, drift is included in reference accuracy.5.8 From page 4-4 of Reference 3.1.14: For errors at reactor pressures above 118 psia and drywell temperatures

_3407F, "instrument accuracy for safety actions (narrow and wide ranges) is not markedly affected by varying drywell temperatures, since the vertical drop of the sensing lines within the drywell as shown in Figure 4.1-1 is approximately equal (+/-1.0 feet). This provides cancellation of temperature effects on the instrument lines, should an elevated drywell temperature condition

[e.g., Loss of Coolant Accident (LOCA)] occur, and thereby ensures continued instrument Setpoint accuracy under these conditions." This assumption is corroborated by as-built elevations for the sensing lines at Grand Gulf. Per Reference 3.1.55, the condensing chambers used by transmitters N091A, B, E, & F, N081A, B, C, & D, are D004A, B, C, and D. From page 1 of Ref. 3.1.55, the condensing chamber, drywell penetration hi, WR lower tap, and WR drywell penetration elevations are as follows: Condensing D004A D004B D004C D004D Chamber Chamber Elevation 2081.004" 2081.412" 2080.872" 2082.564" (overflow elev.)Drw Pen Hi 2000.76" 2000.868" 2001" 2001.12" Drywell El. Drop 80.244" 80.544" 79.872" 81.444" Ref. Leg (Chamber -Pen)WR Lower Tap 1839.996" 1839.996" 1839.996" 1839.996" WR Dry Pen Low 1762.14" 1761.66" 1756.68" 1756.68" Drywell El. Drop 77.856" 78.336" 83.316" 83.316" Variable Leg (Tap -Pen)Difference in 2.388" 2.208" 3.444" 1.872" Drops (Abs Value of Drop Ref Leg-Variable Leg Drop)The vertical drop differences are within that assumed by Ref. 3.1.14 (+/-1.0 feet).Thus, the variations of temperatures within the drywell are not considered, since B (~. CALCULATION SHEET_ ENTERGY SHEET 17 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 the effects will be essentially the same on the reference and variable legs and effectively cancel each other.5.9 A calibration interval of 30 months will be assumed for the transmitters, which is the nominal 24-month period, plus a 25% grace period (Refs. 3.2.6 -3.2.9). A calibration interval of 115 days will be assumed for the trip units (Refs. 3.2.6 -3.2.9)..5.10 The transmitters are conservatively assumed to be compensated for a system operating pressure of 1000 psig (Ref. 3.1.20, 3.1.21). The maximum static pressure at the time of trip is assumed to be equal to the lowest Technical Specification safety relief setting of 1103 psig, plus the +/-15 psi setting tolerance (Ref 3.2.14). Static pressure zero and span effect will apply only to the remaining 118 psi (1103 psig + 15 psi -1000 psig) not compensated for in the calibration process.5.11 Primary Element uncertainty is assumed to be negligible and is therefore not considered.

This is based on the nature of the measurement such that the instrument does not interfere with the process variable and that there is no uncertainty associated with the reference legs.5.12 The error incurred as a result of temperature gradients in the reference leg due to thermal stratification in the drywell and containment is negligible and unlikely.Ref. 3.1.14, Page 4-4.5.13 It is assumed that the water in the reference leg in containment and the drywell is the same as ambient temperature based on the fact that the reference leg is made of long lengths of uninsulated pipe inside containment.

5.14 Static pressure span bias effect is calibrated out (Refs. 3.1.20, 21). For the 1153 Rosemount transmitters, a static pressure correction uncertainty of +/-0.5%reading/1000 psi remains. For the 1152-T0280 Rosemount transmitters, the vendor manual does not provide a similar static pressure correction uncertainty or static pressure span uncertainty (Ref. 3.1.39, Tab 20). Therefore, based on the Rosemount manual for 1152 non-T0280 transmitters (Ref. 3.1.39, Tab 6), a static pressure correction uncertainty of +0.25% reading/1000 psi and a static pressure span uncertainty of +/- 0.81% Reading / 1000 psi is assumed for 1152-T0280 transmitters.

5.15 It is assumed that no error is caused by reduced insulation resistance due to mild environment for first trip conditions (Assumption 5.21).5.16 For the temperatures and pressures considered in the reference legs to determine the density effects, two extremes are considered and compared to the conditions assumed for establishing the calibration parameters of the transmitters.

The two limiting conditions, producing maximum and minimum densities, are defined as follows:

CALCULATION SHEET--~ENTERGY SHEET 18 OF 49 CALCULATION NO. JC-Q 1B21-N681-1 REV. 1 A. Reference leg at low temperature and high pressure, which will produce the maximum density in the reference leg and will have the effect of causing a lower indicated level than actual.B. Reference leg at high temperature and low pressure, which will produce the minimum density in the reference leg and will have the effect of causing a higher indicated level than actual.Because the level 1 trip is a decreasing setpoint, only effects which tend to cause a higher indicated level than actual need be considered.

Thus, only condition B above will be considered in this calculation.

The maximum containment temperature that the sensing lines experience prior to a level 1 trip is conservatively assumed to be 100'F (Reference 3.1.54).A minimum pressure of 1000 psia is assumed based the pressure when the level 1 trip occurs (Ref. 3.1.52, Fig. 1-b for LBLOCA, Fig. 3-b for SBLOCA).5.17 For the Rosemount static pressure span effect, the 'reading' differential pressure is taken as the magnitude of the calibration input value at the analytical limit (-154.7 inches) (Refs. 3.1.20, 3.1.21). For IB21NO81C, with a level range from -160 to 60 inches (220 inches span) and a calibration range of -227.29 to -70.94 inwc (156.35 inwc span):= -[(setpoint (inches) + zero offset)/span (inches)

• span (inwc)] -calibration zero (inwc)= -(-154.7 inches + 160 inches)/220 inches

• 156.35 inwc -(-227.29) inwc= 223.53 inwc The Rosemount 1152 static pressure span effect includes a -1% bias. This effect is calibrated out (Assumption 5.14).5.18 An instrument tap location error of 0.25 inches is conservatively assumed. This is considered a PM error and is a random effect based on survey uncertainty.

5.19 It is assumed the effect of recirculation pump flow past the lower wide-range instrument tap is inconsequential (Ref. 3.1.15). Operation of the recirculation pumps causes a velocity effect at the lower tap, resulting in a reduced pressure and a lower sensed reactor water level. For the Level 1 trip, this bias effect is conservative and will be ignored.5.20 Since Rosemount 51ODU model is obsolete, they may be replaced with 71ODU's in the future (Ref. 3.1.16). The performance specifications for the 710DU are equal to or better than those of the 51 ODU.5.21 The time at which the level 1 trip is assumed to occur for a Small Break LOCA is-90.67 seconds (Ref. 3.1.53). For a Large Break LOCA, the time at which the level 1 trip is assumed to occur is -6 seconds (Ref. 3.2.4 and Ref. 3.1.52, Fig. 1-b). Due to these relatively short time intervals, only normal environmental CALCULATION SHEET-ENTERGY SHEET 19 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. 1 conditions will be used in this calculation for radiation effects and insulation resistance effect. However based on reference 3.1.54, the transmitter will experience an elevated temperature (approximately 101'F) prior to performing its safety function.

This temperature will be considered the maximum accident temperature for the transmitter.

5.22 The operating transient for this calculation is based on a loss of feedwater flow.Per reference 3.2.2, the lowest level during the transient is -95 inches, referenced to the bottom of the steam separator skirt. Per reference 3.2.16, instrument zero is approximately 16 inches above the bottom of the skirt. Therefore, the limiting transient level will be taken as -111 inches.'5.23 The reference leg density condition assumed for transmitter scaling is obtained from reference 3.1.55. The density in the reference leg is shown to be defined by a specific volume of 0.01602 ft 3/lbm with the system pressure at 1005 psig (1020 psia). Per reference 3.2.18, those values correspond to a water temperature of 80'F. Reference 3.1.56 confirms that EPU did not change the nominal pressure conditions.

5.24 Generally, the reference and variable legs will have the same weight of water in them from the lower instrument tap on the reactor to the transmitter, as they the lines are run in relative proximity and can be assumed to contain similar fluid density. Thus, these weights effectively cancel each other when the differential pressure is measured via the transmitter.

In addition, the instrument lines in the drywell are not considered in this calculation, per the methodology of NEDC-31336P (Ref. 3.1.14 and Assumption 5.8). Thus the only density changes necessary for consideration are the reference leg fluid densities for the height of water between the upper and lower drywell penetrations.

For conservatism, this calculation will consider the height between the condensing chamber and the lower instrument tap. In order to maximize this effect, the greatest distance between the two is obtained from Ref. 3.1.55.

MCALCULATION SHEET---ENTERGY SHEET 20 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 6.0 METHODOLOGY

6.1 Device

Uncertainties For each module, the uncertainty terms applicable to this application will be specified and combined into the following module errors: RA -reference accuracy L -negative bias uncertainty M -positive bias uncertainty MTE -measurement and test equipment inaccuracies D -drift 6.2 Loop Uncertainties The random and bias components of: PE -errors associated with the Primary Element PM -errors in Process Measurement, and IR -errors due to degradation in Insulation Resistance will be quantified, the loop error equation given, and the device and loop uncertainties combined to produce: AL -SRSS of all device random uncertainties except drift LL -The sum of all negative bias uncertainties ML -The sum of all positive bias uncertainties CL -SRSS of all measurement and test equipment inaccuracies used for calibration.

DL -SRSS of all drifts Per reference 3.1.14, a single side of interest is used by GE to determine reactor level setpoints.

Accordingly, a factor of 1.645/2 will be applied to the random portions of LU: LU -(1.645/2)*SRSS( AL, CL, PE, PM ) +/- IR -LL + ML 6.3 Total Loop Uncertainty The total loop uncertainty will be calculated using the reference

3.1.1 equation

TLU = LU + DL 6.4 Allowable Value The allowable value for the loop will be calculated using the reference

3.1.1 equation

A CALCULATION SHEET-... ENTERGY SHEET 21 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. 1 AV=AL-LU 6.5 Nominal Trip Setpoint The nominal trip setpoint will be calculated using the reference

3.1.1 equation

NTSP = AL +/- TLU 6.6 Spurious Trip Avoidance The probability of a spurious trip during normal plant operation using the Tech Spec setpoint will be evaluated using the methodology of reference

3. 1.1 and calculated loop errors. Per reference 3.1.1, a 95% probability of no spurious trip is acceptable.

6.7 LER Avoidance The probability of exceeding the Tech Spec allowable value without a trip at the tech spec setpoint will be evaluated using the methodology of reference 3.1.1 and calculated loop errors. Per reference 3.1.1, a 90% probability of avoiding LERs is acceptable.

Note: When considering the probability of a spurious trip, any late actuation will be conservative.

Similarly, when considering the probability of an LER, any early actuation will be conservative.

This means that single sided distributions are appropriate for this evaluation.

Per reference 3.1.1, a Z of 1.645 corresponds to a probability of 95%. Similarly, a Z of 1.28 corresponds to a probability of 90%.6.8 Nomenclature The nomenclature of reference 3.1.1, Section 1.6, will be used. Errors associated with the transmitter will be subscripted with a "1", errors associated with the trip unit will be subscripted with a "2", while loop errors will be subscripted with an"UL. For example, D 1 would be the transmitter drift, D 2 would be the trip unit drift, and DL would be the loop drift.6.9 Worst Case Loop The equipment and environments for each loop are identical; therefore, no worst case calculation is required.

I 'Mh CALCULATION SHEET-ENTERGY SHEET 22 OF 49 CALCULATION NO. JC-OIB21-N681-1 REV. 1 7.0 CALCULATION

7.1 Transmitter

Uncertainties, Rosemount 1153 Using the vendor data from Section 4.4 (Transmitter N081C is used -the slight difference in calibration spans between the transmitters does not result in significant differences in device errors): URL = 750 inwc SPAN = 156.35 inwc RAI = +/- 0.25% span (3a)= +/- 2/3(0.0025)*( 156.35) inwc= +/- 0.27 inwc Temp Effect = +/- (0.75 % URL + 0.5% span) / 100'F (3a)= + 2/3((0.75%)(750 inwc) + (0.5%)(156.35 inwc))/100 0 F= +/- 4.28 inwc /100°F Temperature effect will be broken into TD (65-90'F per reference 3.1.1), TEN (90-95°F, the balance of the normal range from Section 4.2) and TEA (95-101°F, the additional accident range from Sec 4.2).Therefore:

TDI = + (4.28)*(25/100)

+ 1.07 inwc TEN[ = -(4.28)*(5/100) 0.22 inwc TEA 1 = , (4.28) *(6/100)0.26 inwc Per reference 3.1.26, humidity has no effect on the sealed transmitter.

HE =+0.00 inwc Radiation Drift (normal)RD 1 = , 0.00 inwc Assumption

5.6 Radiation

Effect (Accident)

REA 1= +/- 0.00 inwc Section 2.0 I CALCULATION SHEETENTERGY SHEET 23 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 Per Assumption 5.3, the worst power supply variations are taken as +/- 4.0 volts.PSi = + 0.005% span / volt variation (3a)= + 2/3(0.00005)( 156.35 inwc)(4 volts)= 0.03 inwc Seismic Effect SE, = + 0.00 inwc Section 2.0 Overpressure Effect OVP 1 = +/- 0.00 inwc Assumption

5.5 Static

Pressure Effect SPE (zero) = + 0.2% URL / 1000 psi (3Y) Assumption 5.10=+/- 2/3*0.2% (750 inwc)

• 118 psi/ 1000 psi=-0.12 inwc SPE (correction)=

+/- 0.5% reading/ 1000 psi (3a) Assumption 5.10, 5.17= +/- 2/3*0.5% (223.53 inwc)

• 1118 psi / 1000 psi=+0.84 inwc SPE (span) = -0.75% reading / 1000 psi (3y) Assumption 5.10, 5.17= -(2/3)*0.75%

(223.53 inwc)

• 118 psi / 1000 psi= 0.14 inwc SPE 1 = +/- SRSS(SPE (zero), SPE(correction), SPE (span))= SRSS(0.12, 0.84, 0.14)=-0.86 inwc Drift DR 1 = +/- 1.218% span for 30 months with -0.0443% span bias=-0.01218*(156.35 inwc) -0.000443 (156.35 inwc)=+/- 1.91 inwc -0.07 inwc Summarizing for the transmitter (1153): Ai = +/- SRSS(RAI, (TENI + TEAI), PSI, SPE)= -SRSS(0.27, (0.22 + 0.26), 0.03, 0.86)=+/- 1.03 inwc= -0.0 inwc Cl = +/- 0.40 inwc Assumption 5.2 DI= SRSS(DRI, TD 1)= SRSS(1.91, 1.07) inwc- 0.07 inwc=+2.19 inwc -0.07 inwc 7.2 Transmitter Uncertainties, Rosemount 1152 Using the vendor data from Section 4.5 (Transmitter N081 B is used -the slight difference in calibration spans between the transmitters does not result in significant differences in device errors): URL = 750 inwc SPAN = 156.35 inwc RAI = + 0.25% span (3a)= +/- 2/3(0.0025)*( 156.35) inwc= +/- 0.27 inwc The Temperature Effect at the calibrated span is determined as follows: (CalSp-MinSp)

= (X-TE0)MinSp)(Max Sp -Min Sp) (TE @ Max Sp -TE @ Min Sp)(156.35-125)inwc

= (X- 5% span)(750 -125) inwc (1.25% span -5% span)31.35 * (-3.75) = 625X- 3125 X =(31.35 * (-3.75)) + 3125 625= 4.82% span Temp Effect = 4.82% span/100°F (3a)= -2/3*4.82%

• 156.35 inwc / 100°F= -5.03 inwc / 100'F Temperature effect will be broken into TD (65-90'F per reference 3.1.1), TEN (90-95'F, the balance of the normal range from Section 4.2) and TEA (95-101'F, the additional accident range from Sec 4.2).Therefore:

TDI TD 1= +/- (5.03)*(25/l00) af CALCULATION SHEET-C- ENTERGY SHEET 25 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1= 1.26 inwc TEN, = +/- (5.03)*(5/100)

=--0.26 inwc TEA 1 = , (5.03)*(6/100)

=+/-0.31 inwc Per reference 3.1.39, humidity has no effect on the sealed transmitter.

HE, = +/- 0.00 inwc Radiation Drift (normal)RD1= +/- 0.00 inwc Assumption

5.6 Radiation

Effect (Accident)

REAr= +/- 0.00 inwc Section 2.0 Per Assumption 5.3, the worst power supply variations are taken as +/- 4.0 volts.PSI = +/- 0.005% span / volt variation (3y)= +/- 2/3(0.00005)(156.35 inwc)(4 volts)=+/-0.03 inwc Seismic Effect SE 1= , 0.00 inwc Section 2.0 Overpressure Effect OVPI= +/- 0.00 inwc Assumption

5.5 Static

Pressure Effect SPE (zero) = +/- 0.25% URL / 2000 psi (3a) Assumption 5.10= +/- 2/3*0.25%

(750 inwc)

• 118 psi / 2000 psi=+/-0.08 inwc SPE (correction)=

+/- 0.25% reading / 1000 psi (3a) Assumption 5.10, 5.17= +/- 2/3*0.25%

(223.53 inwc)

• 1118 psi / 1000 psi= +/- 0.42 inwc SPE (span)= +/- 0.81% reading / 1000 psi (3a) Assumption 5.10, 5.17= +/- (2/3)*0.81%

(223.53 inwc)

• 118 psi / 1000 psi=+/-0.15 inwc o CALCULATION SHEET SHEET 26 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. 1 SPE 1 Drift= 1 SRSS(SPE (zero), SPE(correction), SPE (span))= +/- SRSS(0.08, 0.42, 0.15)= +/- 0.46 inwc= + 1.218% span for 30 months with -0.0443% span bias= +/- 0.01218*(156.35 inwc) -0.000443 (156.35 inwc)= 1.91 inwc -0.07 inwc DR 1 Summarizing for the transmitter (1152): Al = +/- SRSS(RAI, (TENI + TEAI), PSI, SPE 1)= +/- SRSS(0.27, (0.26 + 0.31), 0.03, 0.46)+/- 0.79 inwc LI =- 0.0 ,inwc MI = + 0.0 inwc C 1 = +/- 0.40 inwc Assumption 5.2 D 1.= +/- SRSS(DRI, TDI)= +/- SRSS(1.91, 1.26) inwc- 0.07 inwc= +/- 2.29 inwc -0.07 inwc 7.3 Trip Unit Uncertainties Using the vendor values from Section 4.6: Span= 156.35 inwc Using transmitter N08 1 C A 2= RA 2=+/- 0.2% span (3a)= +/- (2/3)*(0.002)*(156.35 inwc)+/- 0.21 inwc=- 0.00 inwc+ 0.00 inwc CD 2 D-? = DR2ý=+0.30 inwc 0.00 inwc Assumption

5.7 Assumption

5.11 7.4 Primary Element Accuracy PE= N/A A CALCULATION SHEET-~-ENTERGY SHEET 27 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. 1 7.5 Process Measurement Accuracy Instrument Tap Installation Error PMTap = +/- 0.25 inches Assumption 5.18+/- 0.25 inches / 220 inches

• 156.35 inwc 0. 178 inwc Density Effects Error Per Assumption 5.16, the PM effect due to density is determined from the nominal reference leg conditions used for scaling (cal) as compared to the minimum density at the worst case condition.

The maximum reference leg height is computed from the Condensing Chamber D004D information in Assumption 5.8 as follows: h = Condensing chamber overflow elev. -WR lower tap elev.= 2082.564 -1839.996 inches= 242.568 inches Calibration:

Densityc,, = 1/specific volume Where specific volume equals 0.01602 ft 3/lbm Assumption 5.23 Densityca, = 1/(0.01602 ft 3/ibm

• 1728 in 3/ft 3)= 0.0361238 Ibm/in 3 The pressure produced from the column of water is determined as follows.= h

• Densitycal

• (1 inwc/0.03609 psi)= 242.568

• 0.0361238

• (1 inwc/0.03609 psi)= 242.7952 inwc Minimum Density (Condition B of Assumption 5.16): DensityB = 1/specific volume Where: specific volume = 0.01608128 ft 3/lbm (100'F, 1000 psia) Assumption 5.16, Ref. 3.2.18 DensityB = 1/(0.01608128 ft 3/lbm

• 1728 in 3/ft 3)= 0.0359862 lbm/in 3 The pressure produced from the column of water is determined as follows.

t CALCULATION SHEET SENTERGY SHEET 28 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 HB = h

• Density 8 * (I inwc/0.03609 psi)= 242.568

• 0.0359862

• (1 inwc/0.03609 psi)= 241.8703 inwc The PM due to density effects is therefore:

PMdensity

= Heal -HB= 242.7952 -241.8703 inwc= 0.9249 inwc NEDC-31336 (Ref. 3.1.14) treats the density term as a random variable.

Thus: PMdensity

= +/-0.9249 inwc Total PM Error PM = SRSS(PMtap, PMdensity)

= SRSS(0.178, 0.9249) inwc= -0.9419 inwc= -0.9419 inwc / 156.35 inwc

• 220 inches= 1.33 inches Note that for decreasing trip signals, negative bias errors are ignored in LU and TLU calculations.

7.6 Insulation

Resistance Bias IR = + 0.0 inwc Assumption 5.15 7.7 Loop Uncertainties Using the equations from reference 3.1.1 and the values from above, including the limiting transmitter accuracy for the 1153 (which results in higher LU and TLU): AL = +/- SRSS(A 1 , A 2)= SRSS(1.03, 0.21)-+1.052 inwc-+/-1.052 inwc/ 156.35 inwc

• 220 inches-+/-1.49 inches LL = -L 1 -L, = 0.0 inwc ML = + M , + M, = 0.0 inwc CL = +/- SRSS(C 1 , C 2)-+/- SRSS(0.40, 0.30)= +/- 0.50 inwc

-+-0.50 inwc / 156.35 inwc-+/-0.71 inches DL = SRSS(D 1 , D 2)= + SRSS(2.19, 0.0) -0.07-+/-2.19 inwc -0.07 inwc (Negative drift bias is not required for decreasing setpoint)-+ 2.19 inwc / 156.35 inwc

• 220 inches-+ 3.09 inches Per reference 3.1.1, the margin reduction technique of single side of interest may be employed for setpoints that actuate in one direction only: LU = + 1.645/2

• SRSS(AL, CL, PM)-+ 1.645/2

• SRSS(1.052, 0.50, 0.9419) inwc+ 1.24 inwc-+ 1.24 inwc / 156.35 inwc

• 220 inches-+ 1.75 inches 7.8 Total Loop Uncertainty Per reference 3.1.1, the margin reduction technique of determining TLU by SRSS may be employed for setpoints that require additional margin: TLU = SRSS(LU, DL)-+ SRSS(1.24, 2.19) inwc+ 2.52 inwc+ + 2.52 inwc / 156.35 inwc

• 220 inches-+ 3.55 inches 7.9 Allowable Value AV =AL+LU= -154.7 + 1.75--152.95 inches The Technical Specifications Allowable value of- 152.50 inches is conservative with respect to the calculated AV.7.10 Nominal Trip Setpoint NTSP = AL + TLU= -154.7 + 3.55= -151.15 inches The plant setpoint of -150.3 inches is conservative with respect to the calculated NTSP.

a CALCULATION SHEET-__- ENTERGY SHEET 30 OF _49 CALCULATION NO. JC-Q I B21-N681-1 REV. 1 7.11 Spurious Trip Avoidance Z = ABS(NTSP -XT) / SRSS(Sigmai, SigmaN) Ref. 3.1.1 XT = Limiting Operating Transient Assumption 5.22= -111.0 inches Sigma 1 = (1/n)

• SRSS(AL, CL, DL, PM)n=2= (1/2)

• SRSS(1.49, 0.71, 3.09, 1.33)= 1.88 SigmaN = XT standard deviation= 0 Ref. 3.1.1 Z = ABS(-150.3

-(-111.0))

/ SRSS(1.88, 0.0)= 20.90 This is above the Section 6.6 & 6.7 minimum acceptable Z value of 1.645 for 95%.7.12 LER Avoidance Z = ABS(AV -NTSP) / (1/n*SRSS(AL, CL, DO,)) Ref. 3.1.1= ABS(-152.5

-(-150.3))

/ (1/2)

• SRSS(1.49, 0.71, 3.09)= 1.256 This is below the Section 6.7 minimum Z value of 1.28 for 90% but is deemed acceptable.

A CALCULATION SHEET_.__ ENTERGY SHEET 31 OF 49 CALCULATION NO. JC-Q1B21-N681-1 REV. 1 8.0 TSTF CALCULATIONS (Ref. 3.1.1)8.1 As-Left Tolerance ALT, -Transmitter TSTF-493 Calculation ALT, = RAI= +0.27 inwc Converting to loop current: ALT, = +(0.27 inwc/156.35 inwc)* 16 mA= +/- 0.027 mA ALT 2 -Trip Unit TSTF-493 Calculation ALT, = RA-+/-+0.21inwc Converting to loop current: ALT 2 = +/-(0.2linwc/156.35inwc)*l6mA

-+/- 0.021 mA 8.2 As-Found Tolerance (AFT)AFT, -Transmitter TSTF-493 Calculation The drift value used in this calculation to determine transmitter drift was derived by statistical analysis, therefore per Reference 3.1.1: AFT, = +/-DR 1 DR 1 = +/- 1.91 inwc -0.07 inwc for 30 months AFT, = -1.98 inwc, +1.91 inwc Converting to loop current: AFT, --(1.98 inwc/156.35 inwc)

• 16 mA,= -0.20 mA AFT,+ = +(1.91 inwc/156.35 inwc)

• 16 mA= +0.19mA Then, AFT, =-0.20 mA, +0. 19 mA ina TEG CAILCULATION SHEET-~~ENTERGY SHEET 32 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1 AFT 2 -Trip Unit TSTF-493 Calculation AFT 2 = +/- SRSS(RA 2 , MTE 2 , DR 2) Reference 3.1.1 AFT 2 = + SRSS(0.21, 0.10, 0)= +0.23 inwc Converting to loop current: AFT 2 = +/- (0.23 inwc/156.35 inwc)

• 16 mA= +/- 0.023 mA 8.3 Loop Tolerances ALTL -As-Left Loop Tolerance ALTL = +/- SRSS (ALTI, ALT 2)= +/- SRSS (0.27, 0.21)= +/-0.34inwc Converting to loop current: ALTL = +/- (0.34 inwc/156.35 inwc)

• 16 mA= + 0.034 mA AFTL -As- Found Loop Tolerance AFTL = + SRSS (AFT,, AFT 2)AFTL = -SRSS (1.98, 0.23)= -1.99inwc AFTL+ = + SRSS (1.91, 0.23)= +1.92inwc Converting to loop current: AFTL-- -(1.99 inwc /156.35 inwc)

• 16 mA,= -0.20mA AFTL+ = +(1.92 inwc /156.35 inwc)

• 16 mA= +0.19mA Then, AFTL = -0.20 mA, + 0.19 mA C CALCULATION SHEET___- ENTERGY SHEET 33 OF 49 CALCULATION NO. JC-01B21-N681-1 REV. 1

9.0 CONCLUSION

The Technical Specifications Setpoint and Allowable Value are conservative with respect to the calculated values.

SUMMARY

OF RESULTS SYSTEM B21 LOOP NUMBERS N691A,B,E,F; N681A,B,C,D Calibration units Reactor Level (inwc) (inches)TOTAL LOOP UNCERTAINTY

+ 2.52 + 3.55 LOOP UNCERTAINTY

+ 1.24 + 1.75 DRIFT ALLOWANCE

+ 2.19 +/- 3.09 M&TE +/- 0.50 +/- 0.71 SPECIFIED (inches) CALCULATED (inches)Analytical Limit -154.70 Allowable Value -152.5 -152.95 Nominal Trip Setpoint -150.3 -151.15

SUMMARY

OF CALIBRATION TOLERANCES As-Left Transmitter TSTF-493 (ALT,) +/-0.27 inwc,____ ___ ___ ____ ___ ___ ____ ___ ___ +/-0.027 mA As-Left Trip Unit TSTF-493 (ALT-) +/-0.21 inwc," +0.021 mA-1.98 inwc,+/-1.91 inwc As-Found Transmitter TSTF-493 (AFT 1) -0.20 mA,+0.19 mA As-Found Trip Unit TSTF-493 (AFT2) +/-0.23 inwc,+/-0.023 mA As-Left Loop Tolerance (ALTL) +/-0.34 inwc,_______________________________

+/-0.034 mA-1.99 inwc, As-Found Loop Tolerance (AFTL) +1.92 inwc-0.20 mA,____ ___ ____ ___ ____ ___ ___ +0.19 mA ATrACHMENT I DESIGN VERIICATION JC-Q1B21-N681.1, REV. I SHEET 34 OF 49 Sheet 1 of 1 DESIGN VERIFICATION COVER PAGE E' ANO-1 1] ANO-2 [El IP-2 [IJ]P-3 EJJAF [-]PLP ElPNPS [-VY 0 GGNS [-RBS "]W3 [I NP Document No. JC-Q1B21-N681-1

] Revision No. I Page 1 of 4 Title: Level 1 Setpoint Calculation 0 Quality Related El Augmented Quality Related DV Method: [ Design Review El Alternate Calculation

-] Qualification Testing ATTACHMENT I JC-QIB21-N681-1, REV. I DESIGN VERIFICATION SHEET 35 OF 49 Sheet 1 of 3 IDENTIFICATION:

DISCIPLINE:

Document Title: Level I Setpoint Calculation

[]Civil/Structural

[]Electrical Doc. No.: ..I&C JC-QIB21-N681-1 .Rv. 1 QA Cat.: SR [-Mechanical MMr Coffaro J/fl({ Ct4 (OE-(3 jINuclear Verifier:

[]Other Manager authorization for supervisor performing Verification.

m N/A Print Sign Date METHOD OF VERIFICATION:

Design Review .. Alternate Calculations

-- Qualificaton Test El The following basic questions are addressed as applicable, during the performance of any design verification.

[ANSI N45.2.11 -1974] [NP] [QAPD, Part II, Section 3] [NQA-1-1994, Part 11, BR 3, Supplement 3s-1].NOTE The reviewer can use the "Comments/Continuation sheet" at the end for entering any comment/resolution along with the appropriate question number. Additional items with new question numbers can also be entered.1. Design Inputs -Were the inputs correctly selected and incorporated into the design?(Design inputs include design bases, plant operational conditions, performance requirements, regulatory requirements and commitments, codes, standards, field data, etc. All information used as design inputs should have been reviewed and approved by the responsible design organization, as applicable.

All inputs need to be retrievable or excerpts of documents used should be attached.See site specific design input procedures for guidance in identifying inputs.)Yes Z No El N/A El 2. Assumptions

-Are assumptions necessary to perform the design activity adequately described and reasonable?

Where necessary, are assumptions identified for subsequent re-verification when the detailed activities are completed?

Are the latest applicable revisions of design docwnents utilized?Yes Z No [-] N/A El1 3. Quality Assurance

-Are the appropriate quality and quality assurance requirements specified?

Yes Z No El N/A El ATTACHMENT 1 JC-QIB21-N681-1, REV. 1 DESIGN VERIFICATION SHEET 36 OF 49 Sheet 2 of 3 4. Codes, Standards and Regulatory Requirements

-Are the applicable codes, standards and regulatory requirements, including issue and addenda properly identified and are their requirements for design met?Yes E No 0i N/A nI 5. Construction and Operating Experience

-Have applicable construction and operating experience been considered?

Yes nI No Li N/A Z 6. Interfaces

-Have the design interface requirements been satisfied and documented?

Yes ni No Li N/A Dq 7. Methods -Was an appropriate design or analytical (for calculations) method used?Yes E No Li N/A ni S. Design Outputs -Is the output reasonable compared to the inputs?Yes E No L-- N/A ni 9. Parts, Equipment and Processes

-Are the specified parts, equipment, and processes suitable for the required application?

Yes Li No ni N/A E 10. Materials Compatibility

-Are the specified materials compatible with each other and the design environmental conditions to which the material will be exposed?Yes Li No Lii N/A N 11. Maintenance requirements

-Have adequate maintenance features and requirements been specified?

Yes Li No E] N/A E 12. Accessibility for Maintenance

-Are accessibility and other design provisions adequate for performance of needed maintenance and repair?Yes Li No Li N/A E 13. Accessibility for In-service Inspection

-Has adequate accessibility been provided to perform the in-service inspection expected to be required during the plant life?Yes n No [-] N/A E 14. Radiation Exposure -Has the design properly considered radiation exposure to the public and plant personnel?

Yes [i No Ei N/A ]15. Acceptance Criteria -Are the acceptance criteria incorporated in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?

Yes E No i N/A Li ATTACHMENT 1 JC-QIB21-N681-1, REV. 1 DESIGN VERIFICATION SHEET 37 OF 49 Sheet 3 of 3 16. Test Requirements

-Have adequate pre-operational and subsequent periodic test requirements been appropriately specified?

Yes D No D- N/A M 17. Handling, Storage, Cleaning and Shipping -Are adequate handling, storage, cleaning and shipping requirements specified?

Yes El No D] N/A []18. Identification Requirements

-Are adequate identification requirements specified?

Yes Ij No [1 N/A N 19. Records and Documentation

-Are requirements for record preparation, review, approval, retention, etc., adequately specified?

Are all documents prepared in a clear legible manner suitable for microfilming and/or other documentation storage method?Have all impacted documents been identified for update as necessary?

Yes Z No F] N/A F1 20. Software Quality Assurance-ENN sites: For a calculation that utilized software applications (e.g., GOTHIC, SYMCORD), was it properly verified and validated in accordance with EN- IT-104 or previous site SQA Program?ENS sites: This is an EN-IT-104 task. However, per ENS-DC-126, for exempt software, was it verified in the calculation?

Yes [E No [E N/A Z 21. Has adverse impact on peripheral components and systems, outside the boundary of the document being verified, been considered?

Yes 11 No El N/A Z ATTACHMENT 1 DESIGN VERIFICATION JC-QIB21-N681-1, REV. I SHEET 38 OF 49 Comments / Continuation Sheet Question # Comments Resolution

[ Initial/Date 1 Comments provided by markup. I Comments incorporated.

MJC 10/1/12 4-4-4-4 ____________

4- ____________

4-4-++

ATTACHMENT 2 JC-QIB21-N681-1, REV. 1 OWNER'S REVIEW COMMENTS SHEET 39 OF 49 Comment Department

/ 1 Comment Date No. Reviewer Discipline

/ Comment[ Date Resolution Resolved I Program Res d I I Owner's Review Comments to JC-0IB21-N681-1 (EC 18458) Level 1 Setpoint I Ceneral Ic I ietll~I J Voss EXCEL This calculation computes 8/14/12 None Required Services Corp. uncertainties that are too large to work with the existing Analytical Limit, Allowable Value and Nominal Trip Setpoint.

Various measures are suggested below to reduce the uncertainty values and to provide a solution.

However, because of the very small margin in this parameter, solution to this problem could require adjustment to the Analytical Limit and / or Allowable.

Value and / or Nominal Trip Setpoint.2 :J Voss EXCEL -If the suggested adjustments still do 9/14/12 Setpoint and AV are now conservative.

Services Corp. not provide errors that are acceptable for the setpoint and AV, then consider the removal of MTE (and possibly reference accuracy) from the equations, since the drift values include these terms.

ATTACHMENT 2 JC-QIB21-N681-1, REV. 1 OWNER'S REVIEW COMMENTS SHEET 40 OF 49 Department

/Comment Da Comment Reviewer Discipline

/ Comment Date Resolution Date I Program Resolved Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level 1 Setpoint 3 J Voss EXCEL At this point, it would appear that an 8/14/12 Setpoint and AV are now conservative.

Services Corp. acceptable resolution may not be possible by merely reducing the uncertainties, and changing the required operating conditions, as suggested below. Ifthis proves to be true. the calculation should be prepared in an approach that establishes new, acceptable values.Thus, the calculation will not use the old values for AV to compare for the Z values, etc. It should be positively presented, and then possibly shown at the end that the AV, AL. NTSP (as appropriate) need to be changed.4 J Voss EXCEL Suggest intermediate terms be 8/14/12 Not required.

Setpoint and AV are now Services Corp. expressed to 4 decimal resolution, so conservative.

that we aren't having multiple round-up issues that make for overly conservative values. As is, we are compounding roundups at least at 3 or 4 intermediate computations.

ATTACHMENT 2 JC-QIB21-N681-1, REV. 1 OWNER'S REVIEW COMMENTS SHEET 41 OF 49 C Department Comment Date Comment Reviewer Discipline

/ Comment Date Resolution I No. rormResolved e Program I I- E I L_______ Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level 1 Setpoint ____5 J Voss EXCEL Services Corp.Section 2.0 Design Requirements RWL level I trip is used to generate initiation signals of low pressure emergency core cooling systems. This means that the break is of sufficient size to exceed the capacity of the high pressure system but not sufficient size to rapidly depressurize the RPV. The environmentally limiting condition is the critical size break that slowly lowers level and releases the maximum energy to the environment around the reference legs. All uncertainties should be evaluated at the worst case condition within the design basis.8/14/12 Section design basis now refers to a SBLOCA as well as IBLOCA and LBLOCA.

ATTACHMENT 2 OWNER'S REVIEW COMMENTS JC-Q1B21-N681-1, REV. 1 SHEET 42 OF 49 Department I Comment Department/

Com Reviewer Discipline I.Program Comment Comment Date Resolution Date Resolved I1 I_ _Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level I Setpoint 6 J Voss EXCEL Services Corp.Assumption

5.1 Should

consider Rosemount internal testing and define some uncertainties as 3 sigma as defined by GE setpoint methodology and Rosemount documents.

All Rosemount transmitters are verified by testing to perform better than the reference accuracy prior to shipment.

All Rosemount transmitters are tested verified to perform within the Temperature uncertainty limits prior to shipment.

For T0280 transmitters supplied by GE, the specifications were based on testing during the development of the setpoint methodoloEv document 8/14/12 Per GEXI2000-00134, Rosemount 3-sigma values incorporated.

ATTACHMENT 2 OWNER'S REVIEW COMMENTS JC-QIB21-N681-1, REV. 1 SHEET 43 OF 49-.-.-..-r -Comment Department

/Com Reviewer Discipline

/o I _Program Comment Comment Date Resolution Date Resolved___________________

L I L Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level 1 Setpoint 7 J Voss EXCEL Services Corp.Assumption 5.2 I Recommend a programmatic change to ensure that combined M&TE or Setting tolerance is always less than or equal to reference accuracy when possible and only use setting tolerance where it is not possible to purchase the necessary M&TE equipment.

This may not result in a reduction in the uncertainty for the current calculation unless it can be verified that the M&TE used in the last calibration is equal to or better than the reference accuracy.

If this is verified, then reduce uncertainties to actual M&TE used.S/14/12 Not within the scope of this revision.M&TE error determined per upcoming revision to JS09.8 J Voss EXCEL Assumption

5.3 Evaluate

the 8/14/12 Voltage variation determined per Services Corp. normal output voltage to confirm applicable design documents.

No re-that it is 24 volts, if it is not evaluation required.reevaluate the spread of voltage between actual and the limits of 23 and 28 volts and adjust uncertainty calculation.

This is a small uncertainty and will not make a significant difference in the calculation outcome, but with negative margin any possible reduction is attempted.

ATTACHMENT 2 OWNER'S REVIEW COMMENTS JC-QlB21-N681-1, REV. I Departmen 44 OF4 Comment Department/

Com Reviewer Discipline I N Program Comment Comment Date Resolution Date Resolved Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level 1 Setpoint 9 J Voss EXCEL Assumption 5.6 How does the 8/14/12 The assumption that RD is calibrated Services Corp. calibration interval affect the out and that the dose rates are low is still radiation drift uncertainty?

Any valid for 24 month intervals.

No residual uncertainty caused by the changes required.exposure would be indistinguishable from drift and could be assumed to be included in the drift term. B21-682 states:- The radiation drift for the transmitters and trip units is assumed to be negligible because of the low normal dose rates. Per reference xxx there is no effect on transmitters below 0.1 Mrad.-" 10 J Voss EXCEL Assumption 5.7 The justification 8/14/12 Not so. the Rosemount manual Services Corp. that drift is include in the trip unit specifically says the accuracy is good repeatability term is based on the for 6 months.calibration interval and not on the Rosemount specification.

II J Voss EXCEL Assumption 5.10 Are the panels 8/14/12 Seismic effects no longer considered, so Services Corp. ridged for seismic considerations this is no longer relevant.or is the acceleration amplified by the panel. This should reference the floor spectra and be a design input and not an assumption.

ATTACHMENT 2 JC-Q1B21-N681-1, REV. I OWNER'S REVIEW COMMENTS SHEET 45 OF 49 Department

/ r 1m1 Date Comment Reviewer Discipline

/ Comment Comment Resolution De No. Program I Date I Resolved Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level 1 Setpoint 12 J Voss EXCEL Assumption 5.11 states that there 8/14/12 PE refers to primary element. GGNS Services Corp. is no PE uncertainty; later in the does not consider reference legs to be a calculation an installation primary element.uncertainty associated with the reference legs is identified and calculated.

Revise statement to no PE and remove the reference leg discussion since that is considered as a PM uncertainty later in the calculation.

13 J Voss EXCEL Assumption 5.14 Assumes that 8/14/12 The assumption is that the 1152-T0280 Services Corp. the calibration procedure corrects has a similar uncertainty for static for suppression, elevation and pressure as the regular 1152 density compensation, This transmitters, not that the static pressure should be confirmed by review of is calibrated out. The calibration procedures clearly reflect a static the calibration procedure to verity pressure adjustment.

that the difference in calibration condition and operating condition densities have been considered.

14 J Voss EXCEL Section 5.15 assumes no IR Assumption clarified to state that a 220 Services Corp. uncertainty due to mild second trip time will not invoke IR conditions, the next section errors.identifies reference leg uncertainties due to plant changes. Are the environment changes due to the limiting__________LOCA evaluated for IR changes? _____ ________________

ATTACHMENT 2 JC-QIB21-N681-1, REV. 1 OWNER'S REVIEW COMMENTS SHEET 46 OF 49 Comm Department

/ Comment Date No. ent Reviewer Discipline

/ Comment D ResolutionResoed I o.Program DaeRsle Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level 1 Setpoint Density Error Issues 15 J Voss EXCEL Services Corp.Section 5.16 This section evaluates the density related uncertainties between normal operation and trip required operating conditions.

The assumptions identified are based on conditions that would not be present at the time of trip for this water level. As an example the RPV at zero PSIG, based on the assumed 6 second trip time in GGNS-N E-00018 and the pressure curves, a realistic evaluation of actual trip conditions and density in the vessel and reference legs should be identified.

Unfortunately, the uncertainty associated with PM uncertainty is relatively small in this calculation and the extensive level of effort to evaluate the exact density changes for the event will not result in a large change in uncertainty, except that the uncertainty is applied as a bias.8/14/12 This section has been revised to account for more realistic trip conditions.

ATTACHMENT 2 JC-QIB21-N681-1, REV. I OWNER'S REVIEW COMMENTS SHEET 47 OF 49 Comment Department

/ C eComment mDate No. Reviewer Discipline Comment Date Resolution Resolved I ProgramI II Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level 1 Setpoint 6 J Voss EXCEL Section 5.16 Bounding Condition 8/14/12 The environmental document (E 10.0)Services Corp. B, bullet B identifies a 60 degree is the authority on bounding ambient containment temperature as a conditions.

bounding condition, is this a realistic temperature for plant operations, this appears to be an improper use of the EQ compartment temperature ranges to identify plant conditions.

Tap Error Issues 17 J Voss EXCEL Section 5.18 What is this 8/14/12 This is not considered

'PE' at GGNS.Services Corp. uncertainty considered to be a The error is now considered to be bias effect, the location of all taps random based on survey has been surveyed with a 0.25 uncertainty.

inches tolerance, but there is no reason not to assume as a random uncertainty.

Additionally, there is an assumption that there is PE I uncertainty.Procciro rffpet EIc..n 18 J Voss EXCEL Section 5.17: Would normally 8/14/12 Rosemount states that there is still a Services Corp. expect the static pressure zero static pressure uncertainty even if the effects to be calibrated out. If calibration corrects for static zero effects have been eliminated pressure.during calibration, this would reduce the uncertainty.

Additionally evaluate the high pressure assumption for Static Pressure uncertainty.

Confirm zero uncertainties have not been compensated for during calibration.

ATTACHMENT 2 JC-QIB21-N681-1, REV. 1 OWNER'S REVIEW COMMENTS SHEET 48 OF 49 Department

/ Comment Date Comment Reviewer Discipline

/ Comment Commetve Reso oD No. Program Resolved Owner's Review Comments to JC-01B21-N681-1 (EC 18458) Level 1 Setpoint Other Issues 19 1 Voss EXCEL Justify removing the seismic 8/14/12 Seismic uncertainty no longer Services Corp. uncertainty, it is the largest single considered, based on upcoming revision contributor to channel uncertainty to JS09.20 J Voss EXCEL Services Corp.Sections 5.2 and 6: Should add a paragraph somewhere within the methodology section (6)regarding the change in methodology for consideration of M&TE errors, if this is going to be done. Note that the approach employed (using the greater of the actual M&TE, setting tolerance, or reference accuracy of the device being calibrated) is not covered in the JS-09 methodology.

[For this project, we recommend across the board that the procedures be changed, so that M&TE and Setting Tolerance are equal to or less than RA for the calibrated devices.From the TSTF-493 perspective, this will simplify implementation.

This should also be considered in Sections 5.2 and 6. Use of this approach would slightly reduce calibration errors.]8/14/12 Upcoming revision to JS09 will contain new M&TE methods.

ATTACHMENT 2 JC-QIB21-N681-1, REV. 1 OWNER'S REVIEW COMMENTS SHEET 49 OF 49 Comment Department

/ Comment Date No. Reviewer Discipline

/ Comment Date Resolution Resolved No. I Program IRI Owner's Review Comments to JC-0IB21-N681-1 (EC 18458) Level I Setpoint 21 J Voss EXCEL Section 5.21 and 5.22 uses the 8/14/12 5.22 is an existing assumption not Services Corp. FSAR as a reference, this is changed by 24 MFC. 5.21 has been generally not a good idea, and the revised.reference should be the analysis that supports the FSAR statement.