ML13323A551
| ML13323A551 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/08/2013 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2013/00088, TAC ME9764 JC-Q1B21-N678-1, Rev 2 | |
| Download: ML13323A551 (34) | |
Text
Attachment 2 to GNRO-2013/00088 JC -QIB21-N678-1 Rev. 2 "Reactor Steam Dome Pressure Scram Setpoint"
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) Calculation No: JC-QIB21-N678-1
- 16) Revision: 002 (7
Title:
Technical Specification Setpoint Determination for Reactor Dome 151 Editorial Pressure Scram
['YES ONO
(" System(s): B21
' Review Org (Department): NPE (I&C Design)
(
Safety Class:
z Component Equipmeut/Structure Type/Number:
0 Safety / Quality Related IB21N078A 1B21N678A j* Augmented Quality Program 1B21N078B IB2lN678B
"]Non-Safety Related 1B21N078C 1B21N678C Document Type: J05.02 1B21N078D 1B21N678D (14) Keywords (Descriptionf/opical Codes): setpoint, uncertainty REVIEWS
(')Name/Signature/Date (16) Name/Signature/Date (1 Name/Signature/Date Mry Coffar0 Robin Smith /
Responsible Engineer 0 Design Verifier Supervisor/Approval 5
Reviewer
_M Comments Attached Comments Attached
Revision R
,ecord of ReVISIOn Original issue.
0 Prepared in response to CR-GGN-2004-0038 & CR 2000-0100.
1 Extended calibration interval to 24 months, incorporated results of drift calculations JC-Qi 111-09020. Updated transmitters' environmental zones and parameters per current 2
revision of referenced documents. Revised trip unit calibration interval to 92 days to agree with Technical Specifications. Updated MTE, SE and bias terms to be consistent with current revision of JS09. Updated references and performed general maintenance.
Added TSTF-493 Section 6.0.
I.
U
A CALCULATION SHEET ENTERGY SHEET 3 OF 33 CALCULATION NO.
JC-01B21-N678-1 REV. 002 CALCULATION CALCULATION NO:
JC-011321-N678-1 REFERENCE SHEET REVISION: 002 I. EC Markups Incorporated NONE II. Relationships:
Sht Rev Input Output Impact Tracking No.
Doc Doc Y/N I1.
JS09 0
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E100.0 0
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- 3.
06-IC-1B21-Q-1002 101
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06-IC-1B21-R-0001 105 19 El
- 5.
MS02 0
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- 6.
ABDO0 0
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- 7.
J1281L 021A 000
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- 8.
J1281L 021B 000
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M1077B 0
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- 13.
865E521 002 007
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- 14.
164C5150 001 018 0
- 15.
164C5150 002 017 0]
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- 16.
164C5150 003 018 191
- 17.
184C4571 001 009
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- 18.
J1507A 0
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- 19.
J1507D 0
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- 20.
460000047 0
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- 21.
J0400 0
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- 22.
J0401 0
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- 23.
19 El
- 24.
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- 25.
A0552 0
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- 26.
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- 27.
368X559BA 0
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- 28.
SDC'-B21 0
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- 29.
22A4622 0
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- 30.
0200-047-0128 0
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- 31.
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- CALCULATION SHEET ENTERGY SHEET 4
OF 33 CALCULATION NO.
JC-QIB21-N678-1 REV. 002 II. Relationships:
Sht Rev Input Output Impact Tracking No.
Doc Doc Y/N
- 35.
EAR-E90-0158 000 9
0[]
- 36.
A0012 0
015 9
0[]
- 37.
A0120 0
016 9
0[]
- 38.
J301.0-QS-27.0-15-0 0
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- 39.
EC-QIOOO-86001 0
003 9
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- 40.
460001972 0
300 9
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- 41.
09 °_
- 42.
PERR91-6068 1
09 0
- 43.
865E522 002 006 1
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865E523 002 006 R
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J1507B 0
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- 46.
J1507C 0
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368X544BA 0
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- 48.
368X558BA 0
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- 49.
GEXI2000-00134 0
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1 50.
III. CROSS
REFERENCES:
- 2. Asset Suite Equipment Data Base (EDB)
- 3. "Handbook of Chemistry and Physics, 57th Edition, 1976-1977", published by the Chemical Rubber Co.
- 4. Tech. Spec./TRM Tables 3.3.1.1-1
- 5. UFSAR Section 15.2.1.2.2 IV. SOFTWARE USED:
Title:
N/A Version/Release:
Disk/CD No.
V. DISK/CDS INCLUDED:
Title:
N/A Version/Release Disk/CD No.
VI. OTHER CHANGES:
Related references removed from the calculation: CR-GGN-2000-0100, 169C8394, EAR-E90-0158, CR-GGN-1999-01828 CA9, VMN 460000944
TABLE OF CONTENTS SECTION PAGE 1.0 Purpose and Description..........................................................................................
6 2.0 References.....................................................................................................................
7 3.0 G iven...........................................................................................................................
10 4.0 Assum ptions................................................................................................................
15 5.0 Calculation...................................................................................................................
18 6.0 TSTF Calculations.................................................................................................
25 7.0 Conclusion...................................................................................................................
27 Attachments
- 1. Design Verification (5 pages)
- 2. Owner's Review Comments (1 page)
1.0 PURPOSE AND DESCRIPTION 1.1.
Purpose The purpose of this calculation is to verify the allowable value and nominal trip setpoint for the Reactor Dome Pressure Scram in the Technical Specifications.
1.2.
Setpoint Bases 1.2.1.
Loop Descriptions This loop consists of the instruments 1 B21 -PT-N078A/B/C/D and 11B21-PIS-N678A/B/C/D.
1.2.2. Design Bases Pressure sensors are furnished which, in conjunction with the Reactor Protection System, scram the reactor if reactor pressure increases, encroaching on the required margin of safety established for safety/relief valve setpoints. (Ref. 2.2.22, 2.2.23, 2.2.27) 1.3.
Desin Bases Event(s) 1.3.1.
The DBE for the high dome pressure scram setpoint is the closure of the MSIV's with pressure scram. The normal scram path associated with MSIV closure and High neuron flux are assumed to fail. (Ref. 2.2.45) 1.3.2. When the reactor is operating at less than full power, the high neutron flux scram may not be initiated. Under these conditions, the high dome pressure scram is credited. (Ref. 2.2.29) 1.3.3. Per Reference 2.2.39, the components in these loops are seismic category 1 instruments. Per Reference 2.1.1, 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.
1.4.
Analytical and Technical Specification Limits Analytical Limit Allowable Value Nominal Trip Setpoint (PSIG)
(PSIG)
(PSIG) 1095.0 1079.7 1064.7 Ref. 2.2.1, 2.2.28, 2.2.33
CALCULATION NO.
JC-Q1B21-N678-1 REV. 002
2.0 REFERENCES
2.1.
Relationships 2.1.1. JS09, Setpoint Methodology 2.1.2. Environmental Parameters Specification No. El00.0 2.1.3. Surveillance Procedure 06-IC-I B21-Q-1002 2.1.4. Surveillance Procedure 06-IC-i B2 1-R-0001 2.1.5. MS02 2.2.
Cross References 2.2.1.
ABDO0 2.2.2. Setpoint Control Loop Diagram J1281L-021A 2.2.3. Setpoint Control Loop Diagram J1281L-021B 2.2.4. Setpoint Control Loop Diagram J1281L-021C 2.2.5. Setpoint Control Loop Diagram J1281L-021D 2.2.6. M1077B 2.2.7. 865E520-002 2.2.8. 865E521-002 2.2.9. PPD 164C5150-001, 164C5150-002, 164C5150-003 2.2.10. PPD 184C4571-001 2.2.11. J1507A 2.2.12. J1507D 2.2.13. Rosemount Instruction Manual 4247-1 (Vendor Man. Num. 460000047) 2.2.14. Location Dwg. J0400 2.2.15. Location Dwg. J0401 2.2.16. Not Used 2.2.17. JC-QI 111-09020, Drift Calculation for Rosemount Range Code 9 Gage Pressure Transmitters
Variable 2.2.19. Radiation Zones A0552 2.2.20. 368X543BA 2.2.21. 368X559BA 2.2.22. SDC-B21 2.2.23. 22A4622 2.2.24. Calculation 0200-047-0128 2.2.25. A0014 2.2.26. Not Used 2.2.27. 17-S-06-5 2.2.28.22A3856AA 2.2.29. FSAR Section 15.2.1.2.2 2.2.30. Not Used 2.2.3 1. Not Used 2.2.32. Not Used 2.2.33. Tech. Spec./TRM Tables 3.3.1.1-1 2.2.34. Not Used 2.2.35. A0012 2.2.36. A0120 2.2.37. J301.0-QS-27.0-15-0, Result Of Low Radiation Dose Rate & LO Level LOCA Evaluation For Model 1153 Series B Rosemount Report D8600063 Revision A 2.2.38. EC-Q1000-86001 2.2.39. Asset Suite Equipment Data Base (EDB) 2.2.40. VMN 460001972 2.2.41. "Handbook of Chemistry and Physics, 57th Edition, 1976-1977", published by the Chemical Rubber Co.
CALCULATION NO.
JC-Q1 2.2.42. Technical Specification 3.4.12 2.2.43. Not Used 2.2.44. Not Used 2.2.45. NEDC31336 2.2.46. PERR91-6068 2.2.47. Not Used 2.2.48. Not Used 2.2.49. 865E522-002 2.2.50. 865E523-002 2.2.51. J1507B 2.2.52. J1507C 2.2.53. 368X544BA 2.2.54. 368X558BA
MR CALCULATION SHEET
[
ENTERGY SHEET 10 OF 33 CALCULATION NO.
JC-Q1B21-N678-1 REV. 002 3.0 GIVEN 3.1.
Loop Block Diagram PT:
PIS:
PS:
1 B21-PT-N078A/B/C/D 1B21-PIS-N678A/B/C/D 1 B21-JY-K613A/B/C/D Ref. 2.2.2, 2.2.3, 2.2.4, 2.2.5 Ref. 2.2.2, 2.2.3, 2.2.4, 2.2.5 Ref. 2.2.2, 2.2.3, 2.2.4, 2.2.5 3.2.
Primary Element See Assumption 4.7 3.3.
Instrument Tubing See Assumption 4.7 3.4.
Environmental Data 3.4.1.
Transmitters Instrument 1 B21-PT-N078A 1 B21-PT-N078B 1B21-PT-N078C 1B21-PT-N078D Room Room Room Room Room Panel Reference 1A313 1A311 1A313 1A311 1H22-P004 1H22-P027 I H22-P005 1H22-P026 2.2.2, 2.2.11, 2.2.35 2.2.3, 2.2.12, 2.2.35 2.2.4, 2.2.35, 2.2.52 2.2.5, 2.2.35, 2.2.51 Description Data Reference Environmental Conditions for Instruments 1 B21-PT-N078A/C in room 1 A313:
Normal:
Pressure Expected Temperature Temperature Range Humidity Dose Rate Radiation (Gamma) TID Zone N-068
-1.0 to -0.10 in. wg.
90°F 60OF to 1050F 20% to 90% R.H.
0.011 Rad/Hr.
3.1 X 103 Rads 2.1.2
ft CALCULATION SHEET
_ _ENTERGY SHEET 11 OF 33 CALCULATION NO.
JC-Q1B21-N678-1 REV. 002 Accident*:
Zone A-016 2.1.2 Pressure Temperature Humidity Radiation (Gamma) TID
- See Assumption 4.4 Seismic Conditions:
Curve Set 2 Curve Set 2 100% R.H.
5.6 X 106 Rads (Gamma) 2.84 X 108 Rads (Beta)
Not Required Section 1.3.3 Description Data Reference Environmental Conditions for Instruments 1 B2 1 -PT-N078B/D in room 1 A3 11 Normal:
Pressure Expected Temperature Temperature Range Humidity Dose Rate Radiation (Gamma) TID Accident*:
Pressure Temperature Humidity Radiation (Gamma) TID
- See Assumption 4.4 Seismic Conditions:
Zone N-069
-1.0 to -0.10 in. wg.
90°F 60'F to 105'F 20% to 90% R.H.
0.026 Rad/Hr.
6.3 X 103 Rads Zone A-016 Curve Set 2 Curve Set 2 100% R.H.
5.6 X 106 Rads (Gamma) 2.84 X 108 Rads (Beta) 2.1.2 2.1.2 Not Required Section 1.3.3 3.4.2. Trip Units & Power Supplies Instrument Room Panel I B21-PIS-N678A 1B21-PIS-N678B IB21-PIS-N678C 1 B2 1-PIS-N678D 1B21K613A 1B21K613B 0C703 (Ref. 2.2.2, 2.2.15, 2.2.25) 0C504 (Ref. 2.2.3, 2.2.14, 2.2.36) 0C703 (Ref. 2.2.4, 2.2.15, 2.2.25) 0C504 (Ref. 2.2.5, 2.2.14, 2.2.36) 0C703 (Ref. 2.2.2, 2.2.15, 2.2.25) 0C504 (Ref. 2.2.3, 2.2.14, 2.2.36) 1H13-P691 1H13-P692 11H13-P693 1H13-P694 1H13-P691 1H13-P692
[
ENTERGY CALTCULATION SHEET SHEET 12 OF 33 CALCULATION NO.
JC-01B21-N678-1 REV. 002 IB21K613C 0C703 (Ref. 2.2.4, 2.2.15, 2.2.25) 1H13-P693 1B21K613D 0C504 (Ref. 2.2.5, 2.2.14, 2.2.36) 1H13-P694 Description Data Reference Normal:
Zone N-028 2.1.2 Temperature 69-90°F Pressure
+0.1 to 1.0 in wg.
Humidity 20% to 50% RH Radiation (Gamma) (see note below) 1.75E2 rads (40 yr TID)
Note: Gamma Radiation Dose = 0.5 rnRad x365.25 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> X0ears 1.75E2 Rads hour year day Accident Environment: Rooms 0C504, 0C703 Same as Normal Ref. 2.1.2 Seismic Conditions:
Not Required Section 1.3.3 3.5.
Vendor Data 3.5.1. Transmitter Data Description Data Reference Tag Number IB21-PT-N078A,B,C,D 2.2.2, 2.2.3, Manufacturer:
Rosemount Model Number:
1153GD9PC Span 1500 PSIG / 4 to 20 mAdc Upper Range Limit (URL):3000 PSIG Calibrated Span 15 to 1515 PSIG / 4 to 20 mAdc Reference Accuracy:
+/- 0.25% span (3a)
Drift:
+/- 0.403% Span for 30 months Power Supply:
<0.005% span per volt (3a)
Temperature Effect
+/- (0.75% URL + 0.5% Span)*AT/1000 F (30a)
Humidity:
N/A (0% to 100% RH)
Radiation:
+ 6.0% URL during and after Exposure to 5.19 x 107 Rads TID (7,)
2.2.4, 2.2.5 2.2.20, 2.2.21 2.2.53, 2.2.54 2.1.4, 2.2.39 2.2.40 2.1.4, 2.2.39 2.2.40, 2.2.18 2.2.17 2.2.40, 2.2.18 2.2.40, 2.2.18 2.2.40 2.2.40
A L111UL!'*II IVN IiN U.
i -,-V I D/-I -iN 0/0-1 rITV.
UU/Z Seismic Effect:
SE = +/- 0.5% URL 2.2.40 Seismic Effects (ZPA of 7 g's)
Static Pressure Effect N/A for Gauge pressure device 2.2.40 Overpressure:
Overpressure effects are not applicable 4.13 Radiation Drift:
Radiation Drift effect is not applicable. 2.2.19, 2.2.38, 4.3 3.5.2. Master Trip Unit Data Description Data Reference Tag Numbers I B21-PIS-N678A/B/C/D 2.2.2, 2.2.3, 2.2.4, 2.2.5 Manufacturer Rosemount 2.2.7, 2.2.8, 2.2.9, 2.2.49, 2.2.50 Model 510 DU 2.2.7, 2.2.8,2.2.9, 2.2.49, 2.2.50 OR 710DUOTT Assumption 4.12 Repeatability*:
+/- 0.20% span 2.2.13
- Repeatability based on Adverse Operating Condition and Normal Environment Drift:
N/A Assumption 4.11 Span 1500 PSIG 2.1.3, 2.2.9, 2.2.39 Humidity effects, power supply effects, temperature effects, and drift are included in the reference accuracy.
The trip units are located in a non harsh environment, therefore radiation and radiation drift effects are not applicable.
Static pressure effect and overpressure effect are not applicable to electronic instrumentation.
3.5.3.
Power Supplies Description Data Reference Power Supply Tag Nos.
1B21K613A 2.2.2, 2.2.7 1B21K613B 11B21K613C 1B21K613D 2.2.3, 2.2.8 2.2.4, 2.2.49 2.2.5, 2.2.50
CALCULATION SHEET ENTERGY SHEET 14 OF 33 CALCULATION NO.
JC-01B21-N678-1 REV. 002 Manufacturer GE Model 184C4571P008 2.2.7, 2.2.8, 2.2.10, 2.2.39, 2.2.49, 2.2.50 2.2.7, 2.2.8, 2.2.10, 2.2.39, 2.2.49, 2.2.50 2.2.7, 2.2.8, 2.2.10, 2.2.39, 2.2.49, 2.2.50 2.2.2, 2.2.3, 2.2.4, 2.2.5, 2.2.10 Power Supply Nominal 24.0 volts Range
- See Assumption 4.9 23.0 to 28.0 Vdc
CALCULATION NO.
JC-Q1B21-N678-1 REV.
4.0 ASSUMPTIONS 4.1.
All uncertainty values are assumed to be 2 sigma values unless specified otherwise.
4.2.
The M&TE values are assumed to be less than or equal to the reference accuracy of the individual devices unless the actual M&TE values are greater, in which case the more conservative value will be used.
4.3.
Because of the low dose rate associated with the normal environment for these locations (Total 40 Yr TID < 104), they are not considered "Harsh Conditions" and radiation drift will not be considered. (Ref. 2.2.38) 4.4.
Environmental Uncertainties for the transmitters are assumed to be determined by normal environmental conditions. The transmitter is not required to act under accident (LOCA) conditions, since this condition would lead to depressurization of the Reactor Vessel and prevent loop trip actuation. Containment pressure and temperature are assumed to remain at their normal operating values until the trip occurs.
4.5.
Not Used 4.6.
Not Used 4.7.
The over pressure analysis takes into account the pressure difference between the RPV bottom and the reactor steam dome pressure when establishing the high pressure scram setpoint. Therefore, no additional process measurement accuracy allowance is needed for the pressure difference between the RPV bottom and the steam dome. The process measurement accuracy allowance due to instrument line temperature is estimated to be less than one inch of water. Further, no primary element exists within the loop which could produce a primary element uncertainty; therefore no primary element uncertainty need be considered. (Ref. 2.2.45) 4.8.
The transmitter is not required to function in LOCA accident conditions. Any exposure to an elevated temperature for a short period of time is assumed to produce a negligible insulation resistance (IR) change. In addition, any insulation resistance losses will produce a positive bias which will tend to reduce the calculated uncertainty. (Ref. 2.2.24) Therefore it is conservative to assume IR losses are negligible.
4.9.
The loop power supply is a 24VDC safety related power supply. (Ref. 2.2.2, 2.2.3, 2.2.4, 2.2.5, 2.2.10). The power supply has a full load to no load variance of 23 VDC to 28 VDC.
The power supply is assumed to supply a nominal voltage of 24 VDC. Therefore, the maximum voltage variance will occur from the nominal voltage setting condition to a no load condition. The voltage variance used in the calculation will be 4.5 volts. This allows for the 4 volt change from the nominal condition to the no load condition and a 0.5 volt nominal voltage uncertainty to account for voltage ripple effect.
4.10. Not Used
CALCULATION SHEET
[-ENTERGY SHEET 16 OF 33 CALCULATION NO.
JC-01B21-N678-1 REV. 002 4.11. The accuracy of the Rosemount trip units (+/-0.20% span) is valid for six months (Ref.
2.2.13). A calibration interval of 92 days plus a 25% grace period (115 days) will be assumed for the trip units (Ref. 2.2.33). Therefore, drift is included in reference accuracy.
4.12. The model number of the trip unit is not specified on the PPD 164C5150 (Ref. 2.2.9). It is currently a 510DU2 (except for 1B21N678A which is identified in the EDB as a 710DUOTT) based on the EDB (Ref. 2.2.39) and PERR91-6068 (Ref. 2.2.46). However, this PERR authorized replacement of the obsolete 510DU2 with the 71ODUOTT. The accuracy specifications of the 51ODU can still be assumed after the replacement since the 71ODU has better accuracy specifications.
4.13. Overpressure effects are not applicable because the maximum pressure that the transmitters are subjected to is a pressure of 1100 PSIG (Ref. 2.1.5, 2.2.6), which is below the URL of the transmitter (Ref. 2.2.40).
4.14. A 24 month refuel cycle will be assumed for the transmitters in this calculation. Applying
+25% margin (per Reference 2.1.1) yields a calibration interval of 30 months.
4.15. MTE Per Reference 2.1.1, the M&TE error is normally considered equivalent to the reference accuracy of the trip unit. Per Reference 2.1.4, a Rosemount 710DU Readout Assembly (+/-0.01 mAdc, per Reference 2.2.13) is used to calibrate the Rosemount Trip Unit.
The actual M&TE error (MTE2) for the Rosemount Trip Unit is = +/-0.01 mAdc, which is equivalent to +/- 0.9375 PSIG Output Range = 4 to 20 mAdc Input Range = 0 to 1500 PSIG 1500 PSIG 93.75 PSIG 93.75 PSIG x 0.01 mnade = 0.93 75 PSI 16 mAdc mAdc mAdc This value is less than the equivalent trip unit reference accuracy of +/-0.20% Span = 3.0 PSIG However, Per Reference 2.1.3 and 2.2.39, the trip unit is calibrated to +/- 0.04 mAdc which is equivalent to:
1500 PSIG 93.75 PSIG 93.75 PSIG x 0.04 made = 3.75 PSI 16 mAdc mnAdc mAdc This value is greater than the equivalent trip unit reference accuracy of +/-0.20% Span =
3.00 PSIG and the more conservative of the three values will be used.
MTE for Trip Unit = 3.75 PSIG Per Reference 2.1.4, a Heise pressure gauge (0-2000 PSIG) or equivalent (accuracy +/-
3.75 PSIG) and a Fluke model 45 Digital Volt Meter (accuracy +/- 0.04 mAdc) are used to calibrate the transmitter. The setting tolerance is specified as +/- 0.04 mAdc.
DVM Accuracy:
Output Range = 4 to 20 mAdc
CALCULATION NO.
JC-O1B21-N678-Input Range = 15 to 1515 PSIG = 1500 PSIG 1SO0 PSIG 93.7s PSIG 93.75 PSIG 16
-c
-d x 0.04 mAdc = 3.75 PSI l6mrAdc m'Adc mAdc SRSS of M&TE Terms (MTEI) for transmitter: MTE = {(3.75)2 + (3.75)2}!/2 = 5.30 PSIG This value is greater than the equivalent transmitter unit reference accuracy of
+/-(2/3)*0.25% Span = 2.50 PSIG and setting tolerance. The most conservative of the three values will be used.
MTE for Transmitter = 5.30 PSIG
CALCULATION NO.
5.0 CALCULATION 5.1.
Definitions 5.1.1. Nomenclature The nomenclature to be used in this calculation section will be explained.
5.1.2. Worst Case Calculation A single calculation will be done for the worst case equipment in the worst case environment. The equipment and environment will be detailed.
5.1.3. 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 5.1.4. 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 LU -
SRSS (AL, CL, PE, PM) + IR - LL + ML 5.1.5. Total Loop Uncertainty The total loop uncertainty will be calculated using the Reference 2.1.1 equation:
TLU = LU + DL
NNTE CALCULATION SHEET SHEET 19 OF 33 CALCULATION NO.
JC-01B21-N678-1 REV. 002 5.1.6. Allowable Value The Allowable Value will be calculated using the Reference 2.1.1 equation:
AV= AL +/- LU 5.1.7. Nominal Trip Setpoint The nominal trip setpoint will be calculated using the Reference 2.1.1 equation:
Device Uncertainties 5.2.1. Transmitter Uncertainties Using the environmental and vendor data from Section 3.4 & 3.5:
URL = 3000 PSIG SPAN= 1500 PSIG RAI
= - 0.25% span (3a)
+/- (2/3)*(0.0025)*(1500 PSIG)
= +/- 2.50 PSIG Temperature Effect (Ref. Section 4.5, 4.6)
= +/- (0.75% URL+0.5% Span) *AT/100°F (30)
+/- (2/3)*[(0.0075*3000 PSIG) + (0.005*1500 PSIG)]* (15°F/100°F)
+/-13.00 PSIG Where AT is the maximum temperature variation during normal conditions.
The temperature variation is based on the maximum containment temperature above the normal value. For this case the maximum temperature variation is 150F (105'F
- 90'F). Therefore AT is 150F. The temperature variation assumed during calibration (90'F - 65'F) will be included as a temperature drift. (Ref. 2.1.1)
Temperature Drift TD,
+/- (0.75% URL + 0.5% Span)* AT/100°F (3a)
+/- (2/3)*[(0.0075*3000 PSIG) + (0.005* 1500 PSIG)]* (25°F/100°F)
= +/- 5.00 PSIG Where AT is the maximum temperature variation assumed during calibration. For this case the maximum temperature variation is 25°F (90'F - 65°F). (Ref. 2.1.1)
Therefore AT is 25°F.
Humidity (HE) has no effect on the sealed transmitter.
Radiation Effect RE,
= +/- 6.0% URL during and after 2.2.40 Exposure to 5.19 x 107 Rads TID (y)
Since this transmitter is not expected to perform under accident conditions, radiation effects are not applicable.
REI
= +/- 0.000 PSIG Seismic Effect Section 1.3.3 SE1
=+/-0.000 PSIG Per Sections 3.5.3 & 4.9, the worst power supply variations are 4.5 volts.
PS1
= +/- 0.005% span / volt variation (3G)
+/- (2/3)*(0.00005)*(1500 PSIG)*(4.5 volts)
= +/- 0.225 PSIG Over-Pressure Effects (OVP) refer to those uncertainties that may occur when pressure transmitters see pressures beyond their upper range limit prior to performing their required function. Overpressure effects are not applicable per Section 4.13 OVPI = +/- 0.0000 PSIA SPE, = +/- 0.000 PSIG DR,
= +/- 0.403% Span for 30 months
= +/- 0.403%
- 1500 PSIG
= +/- 6.045 PSIG Radiation Drift (RD):
(Ref. 2.1.2, 2.2.19, 4.3)
RD,
= +/- 0.000 psig Summarizing for the transmitter:
A1
=l SRSS (RAI, TE1, HE1, RE 1, SE 1, PS1, OVP1, SPE1)
= +/- SRSS (2.50, 3.00, 0.00, 0.00, 0.00, 0.225, 0.00, 0.00)
= +/- 3.92 PSIG L
= - 0.000 PSIG MI
= + 0.000 PSIG MTEI = +/- 5.30 PSIG (Ref. section 4.15)
lift CALCULATION SHEET
[
-*-ENTERGY
(*
SHEET 21 OF 33 CALCULATION NO.
JC-QIB21-N678-1 REV. 002 Dl
=-SRSS (DR,, TDI, RD1 )
= + SRSS (6.045, 5.00, 0.0000)
= +/- 7.85 PSIG 5.2.2. Trip Unit Uncertainties Using the vendor data from Section 3.5.2:
SPAN
= 1500 PSIG A2 = RA 2= +/- 0.20% span
= +/- (0.0020)*(1500 PSIG)
= +/- 3.00 PSIG L,)
= - 0.000 PSIG M')
= + 0.000 PSIG MTE2
= +/- 3.75 PSIG Assumption 4.15 D2
= +/- 0.00 PSIG Assumption 4.11 5.3.
Loop Uncertainties 5.3.1.
Primary Element Accuracy (PE)
= +/- 0.000 PSIA Assumption 4.7 5.3.2. Process Measurement Accuracy (PM)
PM =+/-0.000 PSIA Assumption 4.7 5.3.3. Insulation resistance Effects (IR)
IR
= +/- 0.000 inHg Assumption 4.8 5.3.4. Using the equations from Reference 2.1.1 and the values from Section 5.2:
=+/- SRSS (A1, A2)
- +/- SRSS (3.92, 3.00)
=- L --2 = 0.0 psig ML =+MI+M 2 =0.0psig CL
= +/- SRSS (MTE1, MTE2)
- +/- SRSS (5.30, 3.75)
- +/- 6.49 PSIG
CALCULATION NO.
JC-Q1B21-N678-1 REV. 002 DL
=+SRSS (DI, D2)
= +-SRSS (7.85, 0.00)
= +-7.85 PSIG LU
= + SRSS (4.94, 6.49, 0, 0)
=+8.16 PSIG 5.4.
Total Loop Uncertainty TLU
=+(LU+ DL)
=+/--8.16+7.85
= + 16.01 PSIG 5.5.
Nominal Trip Setpoint 5.5.1. TS Setpoint The Analytical Limit for this calculation is 1095 PSIG. (Ref. 2.2.1, 2.2.28)
NTSP = AL - TLU AL = 1095 psig 1095 PSIG - 16.01 PSIG = 1078.99 PSIG Calculated Setpoint = 1079.0 PSIG TRM Setpoint < 1064.7 PSIG (Ref. 2.2.33)
Plant Setpoint = 1064.7 PSIG (Ref. 2.1.3)
Therefore, the TRM and Plant setpoints are conservative.
5.6.
Allowable Value (AV)
Allowable Value
= AL - LU
= 1086.84 PSIG Calculated Allowable Value = 1086.9 PSIG Technical Specification Allowable Value < 1079.7 PSIG (Ref. 2.2.33)
Therefore, the Technical Specification Allowable Value is conservative.
CALCULATION SHEET I0~-
ENTERGY SHEET 23 OF 33 CALCULATION NO.
JC-Q1B21-N678-1 REV. 002 5.7.
Spurious Trip Avoidance For Spurious Trip Avoidance purposes, the Limiting Operating Transient Variation must be calculated at the highest vessel pressure seen during operation since this value would tend to move the process closer to the trip setpoint.
Highest vessel pressure seen during normal operation = 1040 PSIG (Ref. 2.2.1)
INTSP-XrI
,!(AD 2 + (CL) 2 + (DL) 2 XT = Limiting Operating Transient Variation XT =Xo+T+Tc Where:
X0 = Maximum or Minimum Steady State Operating Value
= Normal operating pressure = 1040 PSIG (Ref. 2.2.1)
T
= Magnitude of Limiting Transient Variation
= 5 PSIG (Ref. 2.2.41)
Tc = Modeling or Bias Uncertainty
= 30 PSIG (Ref. 2.2.45)
XT = X0 + T + Tc
= 1040 + 5 + 30
1075 PSIG Z
11064.7 -10751 (1/2)*(4.942 + 6.492 + 7.852)1/2 Z = 1.81 This value meets the minimum Spurious Trip Avoidance criteria of 95% probability, Z>
1.645; therefore, Spurious Trip Avoidance is verified.
4 CALCULATION SHEET SHEET 24 OF 33 CALCULATION NO.
JC-01B21-N678-1 REV. 002 5.8.
LER Avoidance (Ref. 2.1.1, App. A)
From section 1.4, the Tech Spec allowable value = 1079.7 PSIG Z N IAV - NTSPI
-*V A,)2 + (CL) z + (DL) 2 Z =
11079.7 -1064.71 (1/2)*(4.942 + 6.492 + 7.852)1/2 Z = 2.65 This setpoint exceeds the minimum LER avoidance criteria of 90% probability, Z >
1.282; therefore, LER avoidance is verified.
CALCULATION SHEET
-_-_-ENTERGY SHEET 25 OF 33 CALCULATION NO.
JC-01B21-N678-1 REV. 002 6.0 TSTF CALCULATIONS (Ref. 2.1.1) 6.1.
As-Left Tolerance ALTI - Transmitter TSTF-493 Calculation ALT1
= RAi
= +/-2.50 psig Converting to loop current:
ALT1
= + (2.50 psig/1500 psig)
- 16 mA
= +/- 0.026 mA ALT2 - Trip Unit TSTF-493 Calculation ALT?
=
RA2
= +3.00psig Converting to loop current:
ALT2
=
(3.00 psig/1500 psig)
- 16 mA
= +0.03 mA 6.2.
As-Found Tolerance (AFT)
AFT1 - 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,
=
-DR1 DR1
=
+/- 6.045 psig for 30 months AFTI
= + 6.045 psig Converting to loop current:
- AFT,
=
- (6.045 psig/1500 psig)
- 16 mA
= +/-0.06 mA AFT2 - Trip Unit TSTF-493 Calculation AFT2
=
SRSS(RA 2, MTE2, DR2) Reference 3.1.1
CALCULATION SHEET ENTERGY SHEET 26 OF 33 CALCULATION NO.
JC-Q1B21-N678-1 REV. 002 AFT2
= + SRSS(3.00, 0.9375, 0)
= +3.14psig Converting to loop current:
- AFT,
= +(3.14psig/1500psig)*
16mA
= +/-0.03 mA 6.3.
Loop Tolerances ALTL - As-Left Loop Tolerance ALTL
= + SRSS (ALT,, ALT2)
=
+ SRSS (2.50, 3.00)
= +/-3.90psig Converting to loop current:
ALTL
= + (3.90 psig/1500 psig)
- 16 mA
= +0.04 mA AFTL - As-Found Loop Tolerance AFTL
= + SRSS (AFTI, AFT2)
=
+/- SRSS (6.045, 3.14)
=
+6.81 psig Converting to loop current:
AFTL
=
+ (6.81 psig/1500 psig)
- 16 mA
= +/-0.07 mA
7.0 CONCLUSION
The Plant Setpoint and Technical Specification Allowable Value are conservative.
SUMMARY
OF RESULTS SYSTEM B21 LOOP NUMBER N678 TOTAL LOOP UNCERTAINTY
+ 8.16 PSIG DRIFT ALLOWANCE
+ 6.49 PSIG SPECIFIED VALUE CALCULATION ANALYTICAL LIMIT 1095 PSIG ALLOWABLE VALUE 1079.7 PSIG 1086.9 PSIG TRIP SETPOINT 1064.7 PSIG 1079.0 PSIG TRM SETPOINT 1064.7 PSIG 1079.0 PSIG
SUMMARY
OF CALIBRATION TOLERANCES
+2.50 psig, As-Left Transmitter TSTF-493 (ALT,)
+/-0.026 mA
+/-3.006 psig As-Left Trip Unit TSTF-493 (ALT-)
+/-3.00 psig,
+/-0.03 mA As-Found Transmitter TSTF-493 (AFT1)
+/-6.045 psig,
+/-0.06 mA As-Found Trip Unit TSTF-493 (AFT2)
+/-3.14 psig,
+/-0.03 mA
+/-3.90 psig, As-Left Loop Tolerance (ALTL)
+/-0.04 mA
+/-6.81 psig, As-Found Loop Tolerance (AFTL)
+/-0.07 mA
ATTACHMENT I JC-Q1B21-N678-1, REV. 2 DESIGN VERIFICATION FORM SHEET 28 or 33 Sheet 1 of 1 DESIGN VERIFICATION COVER PAGE El ANO-1 n ANO-2
[I IP-2 E] IP-3 E JAF E] PLP
[I PNPS
[3 VY 0 GGNS O]RBS 0 W3 Q NP Document No. JC-Q1B21-N678-1 Revision No.
Page I of 4 2
Title. Technical Specification Setpolnt Determination for Reactor Dome Pressure Scram N Quality Related
[] Augmented Quality Related DV Method:
0 Design Review El Alternate Calculation
[I Qualification Testing VERIFICATION REQUIRED DISCIPLINE VERIFICATION COMPLETE AND COMMENTS RESOLVED {DV print, sign, and date) i[i Electrical L]
Mechanical.
Instrument and Control Robin Smith S-I Civil/Structural
[]
Nuclear 13 Originator:
ATTACHMENT I JC-Q1B21-N678-1, REV. 2 DESIGN VERIFICATION FORM SHEET 29 OF 33 ATTACHMENT 9.6 DESIGN VERIFICATION CHECKLIST Sheet I of 3 IDENTIFICATION:
Document
Title:
Technical Specification Setpoint Determination for Reactor Dome Dracctir r r 0
01 Doc.No.:
JC-QB21-N678-1 Rev.2 QA Cat. 1 U
Robin Smith
/Z0 c///f r-0 Verifier:
Print Sign Date
.- l1 DISCIPLINE:
Civil/Structural Electrical I&C Mechanical Nuclear Other
-i:
Manager authorization for supervisor performing Verification.
El N/A Print Sign Date METHOD OF VERIFICATION:
Design Review 0]
Alternate Calculations 0 Qualification Test 0 The following basic questions are addressed as applicable, during the performance of any design verification. [ANSI N45.2.11 - 19741 [NP QAPD, Part II, Section 3][NP NQA-1-1994, Part I, BR 3, Supplement 35-1].
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 0 No []
N/A C0
- 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 documents utilized?
Yes0 No [
N/A 0
- 3.
Quality Assurance -Are the appropriate quality and quality assurance requirements specified?
Yes Z No El N/A E]
ATTACHMENT I JC-QIB21-N678-1, REV. 2 DESIGN VERIFICATION FORM SHEET 30 OF 33 ATTACHMENT 9.6 DESIGN VERIFICATION CHECKLIST 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 0 NoD N/A C]
- 5.
Construction and Operating Experience - Have applicable construction and operating experience been considered?
Yes [D No D]
N/A 1-
- 6.
Interfaces - Have the design interface requirements been satisfied and documented?
Yes (D No D]
N/A E]
- 7.
Methods - Was an appropriate design or analytical (for calculations) method used?
Yes [D No Dj N/A 1-
- 8.
Design Outputs - Is the output reasonable compared to the inputs?
Yes 0 No []
N/A E]
- 9.
Parts, Equipment and Processes - Are the specified parts, equipment, and processes suitable for the required application?
Yes []
NoD N/A ED
- 10.
Materials Compatibility-Are the specified materials compatible with each other and the design environmental conditions to which the material will be exposed?
Yes []
No D]
N/A Z
- 11.
Maintenance requirements - Have adequate maintenance features and requirements been specified?
Yes Z NoD N/A D7
- 12.
Accessibility for Maintenance - Are accessibility and other design provisions adequate for performance of needed maintenance and repair?
Yes []
No []
N/A Z
- 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 D]
No D]
N/A 0
- 14.
Radiation Exposure - Has the design properly considered radiation exposure to the public and plant personnel?
Yes []
No D]
N/A M
- 15.
Acceptance Criteria - Are the acceptance criteria incorporated in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?
Yes []
No D]
N/A 0
ATTACHMENT I JC-QIB21-N678-1, REV. 2 DESIGN VERIFICATION FORM SHEET 31 OF 33 ATTACHMENT 9.6 DESIGN VERIFICATION CHECKLIST Sheet 3 of 3
- 16.
Test Requirements - Have adequate pre-operational and subsequent periodic test requirements been appropriately specified?
Yes 0 No Dl N/A RI
- 17.
Handling, Storage, Cleaning and Shipping - Are adequate handling, storage, cleaning and shipping requirements specified?
Yes El No El N/A Z
- 18.
Identification Requirements - Are adequate identification requirements specified?
Yes 0 NoLJ N/A Z
- 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 NoD[
N/A LI
- 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 []
No D]
N/A Z
- 21.
Has adverse impact on peripheral components and systems, outside the boundary of the document being verified, been considered?
Yes Z NOD[
N/A LI
ATTACHMENT I JC-QIB21-N678-1, REV. 2 DESIGN VERIFICATION FORM SHEET 32 OF 33 ATTACHMENT 9.7 DESIGN VERIFICATION COMMENT SHEET Comments / Continuation Sheet Question Comments Resolution Initial/Date 1
Comments provided by markup Comments incorporated.
_ I I
4-
+
+
I
+
4-1 4-4-
4
+
ATTACHMENT 2 JC-Q1 B21-N678-1, REV. 2 OWNER'S REVIEW COMMENTS SHEET 33 OF 33
~EnteWg ATTACHMENT 9.10 ENGINEERING CHANGE COMMENT FORM SHEET i OF I Page 1 of I EN-DC-115, Rev. 10