ML20134J501
| ML20134J501 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/04/1996 |
| From: | Vande Visse P COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20134J483 | List: |
| References | |
| 22S-B-004E-189, 22S-B-004E-189-R00, 22S-B-4E-189, 22S-B-4E-189-R, NUDOCS 9611150238 | |
| Download: ML20134J501 (10) | |
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l Exhibit C j NEP-12-02ZI
. R:; vision 1 CALCULATION COVER SHEET Zion Calculation No.: 22S-B-004E-189 -
DESCRIPTION CODE: 10 4 ZION NUCLEAR STATION SYSTEM CODE: RC l
TITLE: Low Temperature Overpressurization Protection (LTOP) Setpoint Calculation I
l REFERENCE NUMBERS l Type Number Type Number PRCJ 4950 1
COMPONENT EPN: DOCUMENT NUMBERS:
EPN Number ComptType Component Doc Type Document Number 1(2)PT-403 DWGC M-9 1(2)PT-405 __ PROC See Section 5.3 1(2)PXX-403 DATA See Section 5.4.1 1(2)PXX-405 CALC 22S-B-004E-166. Rev.1 REMARKS: Calculation has been revised to reflect a reduced minimum acceptable Appendix G l curve pressure of 470 psig.
REV. REVISION APPROVED DATE NO.
1 Reduced Appendix G curve pressure Q, g', G y 4. g 0 Original Issue D.Ewan 5/14/96 Effective 9396 '
9611150238 961108 PDR ADOCK 05000295 p PDR
' Exhibit C NEP-12-02 Revision 3 page 1 of 2 COMMONWEALTH EDISON COMPANY CALCULATION TITLE PAGE J
CALCULATION NO. 22S-B-004E-189 PAGE NO.: 1 OF 9 l
@ SAFETY RELATED 0 REGULATORY RELATED 0 NON- SAFETY RELATED CALCULATION TITLE:
Low Temperature Overpressurization Protection (LTOP) Setpoint Calculation l
l STATION / UNIT: ZION /1&2 SYSTEM ABBREVIATION: RC EQUIPMENT NO. 1(2)PT-403 PROJECT NO. 4950 1(2)PT-405 l
1(2)PXX-403 1(2)PXX-405 REV: 1 STATUS: Approved QA SERIAL hlO.,OF}.qHRON NO. N/A DATE: N/A PREPARED BY: Chuck Hallett h j. DATE: //[h REVISION
SUMMARY
- Revised +he minimum acceptable Appendix G curve RCS pressure to reflect revised loop uncertainty (F aference 5.2.1). Revised static head correction error to agree with instrument location higher than vessel beltline level.
ELECTRONIC CALCULATION DATA FILES REVISED:
(Name ext / size /date/ hour: min / verification method / remarks)
/-189RL bef029a n-9&fsu9:iopm DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION YES O NO 2 i ,n . .
REVIEWED BY: P. VandeVisse %% $([ /#d Y/fse. DATE: //[ d REVIEW METHOD:Md //ex/ COMMENTS (C, NC OR Cl): I APPROVED BY: Dean Galanis C3).6.GM DATE: 11-4 9 6 lssued: 9/3/96
Exhibit C NEP-12-02 Revision 3 page 2 of 2 COMMONWEALTH EDISON COMPANY CALCULATION REVISION PAGE CALCULATION NO. 22S-B-004E-189 PAGE NO.: 2 OF 9 REV: 0 STATUS: Approved QA SERIAL NO. OR CHRON NO. N/A DATE: 5/14/96 PREPARED BY: C. Hallett DATE: 5/9/96 REVISION
SUMMARY
- Initial Issue ELECTRONIC CALCULATION DATA FILES REVISED: NONE l (Name ext / size /date/hourmin/ verification method / remarks) i a
DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION YESO NO@
- 1. REVIEWED BY: S. McCarthy DATE: 5/13/96
- 2. REVIEW METHOD: Detailed Review COMMENTS (C, NC, Cl): NC i
- 3. APPROVED BY: D. Ewan DATE: 5/14/96 I
REV: STATUS: QA SERIAL NO. OR CHRON NO. DATE:
PREPARED BY; DATE:
REVISION
SUMMARY
ELECTRONIC CALCULATION DATA FILES REVISED:
(Name ext / size /date/ hour. min / verification method / remarks)
DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION YESO NOO
- 1. REVIEWED BY: DATE:
- 2. REVIEW METHOD: COMMENTS (C, NC, Cl):
- 3. APPROVED BY: DATE:
w.n.,
Effectwe 9/3/96
Exhibit D NEP-12-02 Revision 3 COMMONWEALTH EDISON COMPANY CALCULATION TABLE OF CONTENTS PROJECT 4950 CALCULATION NO. 22S-B-004E-189 REV. NO.1 PAGE NO. 3 DESCRIPTION PAGE NO. SUB-PAGE NO.
TITLE PAGE 1 CALCULATION REVISION PAGE 2 TABLE OF CONTENTS 3
- 1. PURPOSE / OBJECTIVE 4
- 2. METHODOLOGY / ACCEPTANCE CRITERIA 4 1
- 3. ASSUMPTIONS AND LIMITATIONS 5
- 4. DESIGN INPUT 5
- 5. REFERENCES 7
- 6. CALCULATIONS 9 !
- 7.
SUMMARY
AND CONCLUC!ONS 9 l ATTACHMENTS NONE i i
i i
4 i lasued. 9/3/96 l
COMMONWEALTH EDISON COMPANY CALCOLATION NO. 22S-B-004E-189 PROJECT NO. 4950 PAGE NO. 4 )
l
- 1. PURPOSE / OBJECTIVE :
I The purpose of this calculation is to determine a minimum Reactor Coolant System (RCS) l pressure to be used in the development of new Appendix G Heatup & Cooldown Curves. '
The minimum pressure will be based upon the existing Low Temperature Overpressurization l Protection (LTOP) Power Operated Relief Valve (PORV) setpoints, minimum RCS temperature of 60*F, and simultaneous operation of one Residual Heat Removal (RHR) Pump and one !
Reactor Coolant Pump (RCP). The minimum pressure will also account for instrumentation ,
uncertainty, transmitter elevation static head and the American Society of Mechanical }
Engineers (A.S.M.E) Code Case N-514 maximum vessel pressure. '
- 2. METHODOLOGY / ACCEPTANCE CRITERIA 2.1 Methodology The RCS Heatup & Cooldown Curves are determined by analysis of reactor vessel weld properties, radiation exposure, etc. These curves represent operationallimits for RCS pressure and temperature at low temperature operation, i.e. during heatup and cooldown. l l'
The calibrated PORV setpoint is calculated to ensure there is a high degree of confidence that the operationallimit is not exceeded..
A.S.M.E. Code Case N-514 [5.1.3] " Low Temperature Overpressure Protection Section XI, 4 Division 1" states "LTOP systems shall limit the maximum pressure in the vessel to 110% of the pressure determined to satisfy Appendix G, para. G-2215 of Section XI, Division 1" Therefore the PORV setpoint value may be based on 110% of the Appendix G curve operationallimit. The Code Case N-514 maximum pressure is designated Puo.
The Appendix G pressure limit refers to the pressure at the vessel beltline region, which region encompasses the center of the reactor core. The core centerline is the reference for all static and dynamic pressure corrections in this calculation.
The operationallimit (PApp G eunre) is reduced by the following factors:
AP due to PORV overshoot (APeoav).
. AP between the transmitters and core centerline to account for dynamic head loss due to running the maximum permitted combination of RCPs and RHR pumps at 65'F (AP ump). p
. static head effect due to differences between the core centerline and transmitter elevations (AP i ).
. instrument uncertainty (P nwum.nt i une.anty).
The Total Loop Errors calculated in Reference 5.2.1 are incorporated herein. Methodologies and references which pertain to incorporating the Total Loop Error are not repeated in this calculation.
REVISION NO, 1
COMMONWEALTH EDISON COMPANY dALCULATION NO. 22S-B-004E-189 PROJECT NO. 4950 PAGE NO. 5 2.2 Acceptance Cnteria The existing PORV setpoint of 407 psig is adequate to ensure a high degree of confidence that the Code Case N-514 operational limit is not exceeded..
- 3. ASSUMPTIONS AND LIMITATIONS None
- 4. DESIGN INPUT 4.1 Current LTOP setpoints [5.4.1) 1PXX-403 407 psig 2PXX-403 407 psig 1PXX-405 407 psig 2PXX-405 407 psig P igni is the bistable setting pressure where the Power Operated Relief Valves will open.
P igni = 407 psig 4.2 Transmitter Elevation Static Head The calibration of the RCS Wide Range Pressure Transmitters are not compensated for static head between their mounted elevation and the reactor core centerline [5.3.6,5.3.7,5.3.8, 5.3.9]. Three transmitters are mounted at 574' 2" and one at 574' 5"[5.4.1).
As depicted in Reference 5.4.2, the core centerline is at elevation 572' 9".
For purposes of conservatism, the largest static head will be used as the P.w variable.
where p = 62.453 lbm/ft' at 60*F and 407 psig [5.5.1]
AP , = (h,, - h_.,,,,,,,.) e p (574 '5"-572' 9") 62.453 1.667 ft . 62.453 lbm lbm
~
ft* _
ft' z
144 in 144 n 2 i l
ft 2 ft 2 i
= 0.72 psi Since the transmitteris at a higher elevation than the core centerline, r assure sensed at the transmitter is always lower than core centerline pressure by a quantity equal to AP w. Therefore ignoring all other condierations, P igni = PA,,o co, - AP w. )
4 1
REVISION NO. 1
COMMONWEALTH EDISON COMPANY ,
CALCU'LATION NO. 22S-B-004E-189 PROJECT NO. 4950 PAGE NO. 6 4.3 PORV Overshoot ,
The PORV Overshoot is the difference between the maximum RCS pressure reached while the (
PORV strokes open in response to a pressure excursion and the PORV setpoint. ;
1 The maximum RCS pressure reached is determined from data in Reference 5.2.4:
1 Setpoint PORV Open Maximum RCS l Assumed Stroke Time Pressure Reached i psig seconds (Pw) psig 400 2 442 4 450 500 2 542 3
4 548 i
4
. The current LTOP Setpoint is 407 psig (4.1) i The PORV Open Stroke time is 3.4 seconds (5.3.2, 5.3.3, 5.3.4]
It is first necessary to determine the maximum RCS pressure reached at 2 and 4 seconds for 407 psig through interpolation Max RCS Press @ 2 seconds 500-400= 542- 442 * (407 - 400) + 442
. = 449 psi Max RCS Press @ 4 seconds =
500-400 * (407- 400) + 450
= 45686 psi The maximum RCS pressure reached at 3.4 seconds is interpolated Max RCS Press @ 3.4 seconds 4-2 = 456.86- 449 * (34- 2) + 449
= 454.5 psi AP,ony = P,. c ,,,,, - 3P ,,
= 454.5- 407
= 47.5 psi 4.4 RCP/RHR Pump Operation induced AP errors APeum, represents the dynamic headloss between the core centerline and the RCS hot legs.
Pump operations between 65'F and 70*F are limited by Reference 5.3.5 to one RCP and one RHR pump. AP errors induced by this pump combination is 22.6 psi (5.2.3].
AP,um, = 22.6 psi REVISION NO. 1
COMMONWEALTH EDISON COMPANY CALCUi.ATION NO. 22S-B-004E-189 PROJECT NO. 4950 FAGE NO. 7 4.5 Instrument Uncertainty The total loop uncertainty as calculated in Zion Calculation 22S-B-004E-166, "COMS/LTOP Pressure Instrument Loop Accuracy Calculation"[5.2.1)is 38.0 psi.
P i nwum.ni unewi.n, = 38.0 psi
- 5. REFERENCES 5.1 METHODOLOGY 5.1.1 TID-E/l&C-10 Rev. O, " Analysis of Instrument Channel Setpoint Error & Instnament Loop Accuracy",
5.1.2 TID-E/l&C-20 Rev. O, " Basis for Analysis of Instrument Channel Setpoint Error & Loop Accuracy",
5.1.3 American Society of Mechanical Engineers Cases of ASME Boiler and Pressure Vessel Code Case N-514, February 12,1992 5.2 CALCULATIONS 5.2.1 22S-B-004E-166 Rev.1, "COMS/LTOP Pressure Instrument Loop Accuracy Calculation" 5.2.2 Westinghouse Letter CWE-93-181, dated 10/4/93 " Commonwealth Edison Company Zion Uniu 1 & 2 Evaluation of COMS Analyses" 5.2.3 lbid., page 11, Table 3: Pressure Differentials Zion Units 1 and 2 5.2.4 lbid., page 16, Table 4: Pressure Overshoot Due to Mass injection Transients Zion Units 1 and 2 (Current Values) 5.3 ZION STATION PROCEDURES 5.3.1 NEP 12.02, Rev. 2 " Preparation, Review, and Approval of Calculations" 5.3.2 PT-27A1-ST, Rev 4 " Pressurizer PORV and Block Valve Stroke Time Test With RCS Less Than 320*F" 5.3.3 PT-27A2-ST, Rev. 3 " Pressurizer PORV and Block Valve Stroke Time Test With RCS Greater Than 320*F" 5.3.4 PT-27A3-ST, Rev. O " Pressurizer PORV and Block Valve Stroke Time Test With RCS Less Than 200*F" 5.3.5 GOP-1, Rev.11 " Plant Heatup" 5.3.6 IMTS-1P-403, Rev.1 " Reactor Coolant Wide Range Pressure Transmitter" 5.3.7 IMTS-1P-405, Rev. 2 " Reactor Coolant Wide Range Pressure Transmitter" REVISION NO. 1
COMMONWEALTH EDISON COMPANY CALCdLATION NO. 22S-B-004E-189 PROJECT NO. 4950 PAGE NO. 8 5.3.8 IMTS-2P-403, Rev. 2 " Reactor Coolant Wide Range Pressure Transmitter" !
l 5.3.9 IMTS-2P-405, Rev.1 " Reactor Coolant Wide Range Pressure Transmitter' i 5.4 ZION STATION DRAWINGS 5.4.1 Comed Instrument Database (IDATA), Specific Data Sheet, and Supplemental Data Sheet for the following instruments:
1PT-403 Rev. D 1PXX-403 Rev. B 1PT-405 Rev. D 1PXX-405 Rev. B 2PT-403 Rev. C 2PXX-403 Rev. B 2PT-405 Rev. C 2PXX-405 Rev. B 5.4.2 M-9 Rev. F " General Arrangement Sections A-A & B-B Zicn Station Unit No.1 & 2" 5.5 MISCELLANEOUS 5.5.1 A.S.M.E. Steam Tables i
REVISION NO. 1
COMMONWEALTH EDISON COMPANY CALCdLATION NO. 22S-B-004E-189 PROJECT NO. 4950 PAGE NO. 9
- 6. CALCULATIONS This calculation will determine the rai+71um pressure to be used by Westinghouse to develop new Appendix G Heatup/Cooldown curves based upon the current LTOP setpoint.
The new RCS pressure will be designated as PApp 0 curve Per A.S.M.E. Code Case N-514 the LTOP system shall limit the maximum pressure in the vessel to 110% of the Appendix G Curve, therefore; Pm = 110% . PApp G curve The LTOP setpoint is derived by; I P,. = P,,, - AP. - APay - AP,, - 8, , uo tv by substitution:
i P,,, = (110% P,,, o ,,,,,) - F,,,, - # goy, - F,,,,, - 8,,, rum.at u c i y I
_ P., + AP. + APov + AP, + 8,,,,,,,, unc.. y p A,o cuiv. -
11 0 Substituting the design input values:
P,,,o,,,,, = 407 psig + 0.72 psi + 47.5 psi + 22.6 psi + 38.0 psi 1.10
= 468.84 psig l I
Rounded !
PApp G curv. = 469 psig
- 7.
SUMMARY
AND CONCLUSIONS 7.1 The minimum acceptable Appendix G Curve Pressure, based upon the current LTOP setpoint is 469 psig @ 60'F.
FINAL PAJE REVISION NO. 1
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Attachment B l
i Zion Calculation No. 22S-B-004E-166, Revision 1 d