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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18066A6641999-09-30030 September 1999
Proposed Tech Specs Re Surveillance Implementation
ML18066A6501999-09-17017 September 1999
Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8
ML18066A5911999-07-30030 July 1999
Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432
ML18066A5691999-07-19019 July 1999
Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS
ML18066A5011999-06-11011 June 1999
Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9
ML18068A5851999-05-0303 May 1999
Proposed Tech Specs Section 3.5,converting to ITS
ML18066A4551999-04-0707 April 1999
Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1
ML18066A4431999-03-30030 March 1999
Proposed Tech Specs Section 3.7,converting to ITS
ML18066A4251999-03-22022 March 1999
Revised TS Pages for ITS Section 3.4
ML20207B2501999-03-0101 March 1999
Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS
ML18066A3281998-11-0909 November 1998
Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17
ML20195E4451998-11-0909 November 1998
Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI
ML20154N2901998-10-12012 October 1998
Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs
ML18066A3021998-09-14014 September 1998
Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages
ML20151Z8111998-09-14014 September 1998
Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1
ML18066A2011998-06-17017 June 1998
Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses
ML18066A1841998-06-10010 June 1998
Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period.
ML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML20217C3101998-03-24024 March 1998
Palisades,Review of Actual Fluence Determination
ML18065B1801998-03-13013 March 1998
Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML18067A8161998-01-26026 January 1998
Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20
ML18066A4901998-01-20020 January 1998
Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A7071997-10-0101 October 1997
Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12
ML18067A6731997-09-0303 September 1997
Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys
ML18067A6771997-09-0303 September 1997
Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16
ML18067A6001997-06-27027 June 1997
Proposed Tech Specs Revising Electrical Power Systems
ML18067A4701997-03-28028 March 1997
Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174
ML20137H5901997-03-27027 March 1997
Proposed Tech Specs Change Request Re Change in Co Name
ML18067A4531997-03-26026 March 1997
Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065B0331996-10-25025 October 1996
Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS
ML18065B0171996-10-18018 October 1996
Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR
ML18065A9551996-10-0202 October 1996
Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves
ML18065A9111996-09-0404 September 1996
Proposed Tech Specs 3.7, Electrical Power Systems.
ML20117K9581996-09-0303 September 1996
Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments
ML18065A8631996-08-14014 August 1996
Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A5861996-03-29029 March 1996
Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
1999-09-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
ML20137G3581996-02-15015 February 1996
Rev 6 to CPC Pnp Process Control Program
ML18064A8141995-06-29029 June 1995
Procedure EOF App B, INPO Emergency Response Assistance Agreement, Dtd 950426
ML20100H2621995-06-18018 June 1995
Rev 2 to Reactor Vessel Exam Program Plan Interval 2,Period 3 & Interval 3,Period 1
ML18064A8881995-03-16016 March 1995
Rev 0 to Palisades Nuclear Power Plant Third Interval ISI Program for Class 1,2 & 3 Components & Supports, Vols I & II
ML18064A6301995-03-0303 March 1995
Rev 7 to App H, Emergency Planning EOF Training Matrix.
ML18064A6341995-02-27027 February 1995
Project Plan,Alloy 600,Palisades Nuclear Plant, Rev 1,dtd 950227
ML20072K7741994-07-15015 July 1994
Rev 0 to Palisades Performance Enhancement Plan
ML20072K7641994-07-0606 July 1994
Rev 1 to Palisades Plant Restart Plan from 1994 Forced Outage
ML18059B0481994-06-0303 June 1994
Attachment 4 to Procedure EM-09-13,Rev 1, ISI Pressure Testing Program Procedure.
ML20069D3081994-05-24024 May 1994
Suitability,Training & Qualification Plan
ML20069G2511994-05-20020 May 1994
Rev 30 to Procedure MO-7A-2, Emergency Diesel Generator 1-2 (K-6B)
ML20069G2391994-05-20020 May 1994
Rev 30 to Procedure MO-7A-1, Emergency Diesel Generator 1-1 (K-6A)
ML20064E4831994-03-0606 March 1994
ASME Section XI Repair Program, 0054-00101-001-100,rev 0
ML20064E5011994-03-0404 March 1994
Procedure for Application & Exam of Weld Overlay Repairs to Austenitic Stainless Steel Piping Systems, 0054-00101-001-101,rev 0
ML18059A6981994-02-23023 February 1994
Reactor Vessel Integrity Project Plan.
ML18059A6881994-02-15015 February 1994
Editorial Changes to Rev 6 to Emergency Implementing Procedure EI-6.13, Protective Action Recommendations for Offsite Populations.
ML18059B0201993-12-31031 December 1993
Methods of Alleviating Adverse Consequences of Fluctuating Water Levels in Great Lakes - St Lawrence River Basin, Rept to Govts of Canada & Us,Dtd 931231
ML18059A5541993-11-19019 November 1993
Rev 4 to Attachment 3 to Procedure REC-1, Recovery Plan Format.
ML18059A4781993-10-27027 October 1993
Rev 5 to Administrative Procedure 9.11, Engineering Analysis.
ML18059A4231993-10-0707 October 1993
Rev 0 to Palisades Plant Pressurizer Safe End Crack Repair Action Plan.
ML20059A5181993-09-30030 September 1993
Public Version of Rev 36 to General Ofc Emergency Planning Procedure,App G, Emergency Telephone Numbers. W/931019 Release Memo
ML18058B7871992-12-15015 December 1992
Rev 3 to HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18058B0341992-05-11011 May 1992
Rev 6 to Odcm.
ML18058A4331992-05-0707 May 1992
Rev 5 to General Ofc Emergency Planning Procedure EOF-4, Communication Support Team, Page 3,reflecting Editorial Changes
ML20090A3401992-02-27027 February 1992
Rev 5 to ODCM
ML18058A1461992-01-27027 January 1992
Rev 45 to General Office Emergency Planning Gort/Eof Procedures Index
ML18058A1471991-12-0909 December 1991
Rev 5 to General Ofc Emergency Planning Procedure EOF-3, Emergency Operations Facility Administrator. Approval Summary Encl
ML18058A1441991-12-0909 December 1991
Rev 5 to General Ofc Emergency Planning Procedure EOF-4, Communication Support Team. Approval Summary Encl
ML18058A1451991-12-0909 December 1991
Rev 6 to General Ofc Emergency Planning Procedure EOF-2, Emergency Operations Facility Director. Approval Summary Encl
ML20091S2361991-12-0909 December 1991
Rev 8 to General Ofc Emergency Planning Procedure GEN-3, On-Shift Sys Power Controller. Approval Summary Encl
ML18058A1421991-12-0909 December 1991
Rev 7 General Office Emergency Planning Procedure GORT-1, General Office Response Team (Gort). Approval Summary Encl
ML18058A1431991-12-0909 December 1991
Rev 10 to General Ofc Emergency Planning Procedure GEN-1, Overview. Approval Summary Encl
ML18057B3281991-10-17017 October 1991
Rev 2 to Procedure EI-15.2, Quarterly Communications Test Telephone Number,Verifications.
ML20086T2811991-09-16016 September 1991
Rev 0 to Functional Description FC-888,covering Replacement of All Four Channels of Reactor Protection Sys Power Supply Assemblies,Trip Unit Assemblies,Interconnection Modules, Bistable Trip Units & Auxiliary Trip Units
ML18057B0221991-05-10010 May 1991
Rev 15 to EM-09-04, Inservice Testing of Selected Safety- Related Pumps, Reflecting Complete Rewrite of Procedure to Omit Vertical Lines
1998-04-29
[Table view] |
Text
ENCLOSURE 2 Consumers Power Company Palisades Plant Docket 50-255 December 1, 1988 CALCULATION OF LOOP ACCURACIES FOR ROSEMOUNT TRANSMITTERS DURING A SMALL BREAK LOCA 7 Pages OC1188-0207-NL02
- E:12(>1 050002!5!'5 PDC
(@ , consumers Power PALISADES NUCLEAR PLANT EA - RJC-83-01 l'llWEIU"5 ENGINEERING ANALYSIS WORKSHEET Sheet of ~'--~-
M.ICHlfiAtn PftlllilUSS Title Ca]cu]atjon of ] oop accm:acj es for: Bosemi:rnn t: t:r:ansmitters d11rfog a small break LOCA.
INITIATION AND REVIEW 1n1t1ated ln1t1ator Review Method Check {J) Technically Reviewed Reviewer Rev Appd Appd
- By Date Alt Det Qua I By Date Descr1pt1on By Cale Rvw Test By A I 0 Original Issue 4. ._ l.1iJ /,/ ZI J/J. rd..:;;' ./ JIA.. ,.,.~ ,,-( l~fltl
\
~
See the attached sheets 2-7 for Analysis.
~
~
- @* consumers Power NUCLEAR OPERATIONS DEPARTMENT EA - RJC-88-01 company Analysis Continuatfon Sheet Sheet 2 of 7 rs~v. o--
- b"ective To calculate loop accuracies for a number of different indicating loops. The loops for which calculations are to be performed are:
- 1. PT-0105A & B
- 2. PT-0104A & B
- 3. PT-0751A-D and PT-0752A-D
- 4. PT-1805A and PT-1812A
- 5. LT-0103
- 6. PT-1814 and PT-1815 The accuracies will be calculated for a small brea_k Loss of Coolant Accident (LOCA) only.
Analysis Input
- 1. EA-KAT-87-01 (Vendor Drawing E-48 Sh 6DT} for methods. receivers. readability accuracies. spans and ranges
- 2. EA-RLS-87-01 (Vendor Drawing E-48 Sh 6ED) for new spans and ranges
- 3. Rosemount data sheet specifications for computing instrument error resulting from harsh environments 4.* FC-567 core cooling instrumentation for new control-span on PT-0105A & B
- 5. Technical Specification Surveillance Procedure RI-69 *subcooling Margin Monitor* for accuracy on SMM-0114 and _SMM-0124.
Assumptions . * *
- 1. The use of Rosemount error specifications is conservative sfoce Rosemount LOCA testing environment is significantly more harsh than the Palisades small break LOCA environment.
- 2. Radiation effects on the transmitter loop during a small break LOCA are insignificant and neglected.
During a small break LOCA no fuel failure is postulated. thus no large radiation fields will be present.
References 1*. EA-KAT-87-01 (Vendor Drawing E-48 Sh 6DT}
- 2. EA-RLS-87-01 (Vendor Drawing E-48 Sh 6ED)
- 3. 950 M206B Sh 4 Instruction Manual (includes specifications on accuracy) for Rosemount 1153D
- 4. 950 M206B Sh 16 Instruction Manual (includes specifications on accuracy) for Rosemount 1154
- 5. 950 M206AC Sh 6 - EEQ file for PT-1814 and PT-1815 Analysis This analysis will be broken up into sections as divided in the objective. For similar loops one calcula-tion will be performed which applies to all the loops. Table 1 summarizes the accuracies in engineering units.
Total 19op error is comprised of errors associated with: a) transmitter as a result of harsh environment.
b) the indicator as a result of normal environment and c) the indicator readability.
~r*iqq_1661A-TC01.
(@ consumers Power company NUCLEAR OPERATIONS DEPARTMENT Analysis Continuation Sheet EA - RJC-88-01 Sheet 3 of r?cv.
7 o--
~Analysis (continued)
The following will define these three components:
ExMTR = Transmitter as a result of environment ERCVR = Normal indicator error ER = Indicator readability error The transmitter harsh environment error is quite large relative to the transmitter's normal environment error. The harsh erro.r masks the normal environment error, therefore the normal environment error will be neglected.
The transmitter harsh environment error is composed of two components, error associated with radiation and*
error associated with temperature/steam. As .stated in Assumption 2, the radiation present in a small break LOCA is minimal and the radiation error is negligible and* will not be used for these calculations.
Rosemount has*performed qualification of transmitters to IEEE-323-1974 as stated in References 3 and 4.
Reference 3 is for Model 1153 transmitters and Reference 4 is for.Model 1154 transmitters. Reference 3 will also be used for Model 1152 transmitters. Based on References* 3 and 4, the following formulas will be used to calculate ExMTR*
1152/1153 - ExMTR = +/- (4.5S URL + 3.5S SPAN) 1154 - ExMTR = +/- (2.5S URL + 0.5S SPAN)
These formulas will be used for all cases with' the exception of PT-1805A, PT-1812A, PT-1814 and PT~1815.
These transmitters are located outside the containment. They are not affected by small break LOCA and accuracy will be the transmitters normal error. The norinal error for PT-1812A and PT-1805A is +/- 0.25S CS per References 3 and 4 for the respective model. For PT-1814 and PT-1815 the normal error is 0.5S CS per Reference 5. The loop error* will be calculated using the root-sum square (RSS) method for combination of ExMTR and ERCVR* Then the readability error will be added and the result will be loop error, EL*
Conclusion Table 1 summarizes the findings of calculations performed for the transmitter loops. These errors are con-sidered extremely conservative for the small break LOCA condition.
MI1188-1661A-TC01
(§) cansumen Power company NUCLEAR OPERATIONS DEPARTMENT Analysis Continuation Sheet EA - RJC-88-01 Sheet 7 TABLE 1 TOTAL ERROR TRANSMITIER RECEIVER SPANS SB LOCA IO NO LOC IO NO ERCVR EREAO URL cs (CS UNITS) CALC NO 1 PT-0104A CONT PI-0104 .5% cs ol 3000 PSIG 600 PSIA +/- 78 PSI 1 2 PT-0104B CONT PTR-0125 1% cs 5 PSI 3000 PSIG 600 PSIA +/- 84 PSI 2 3 PT-0105A CONT PI-0105A 1% cs 25 PSI 3000 PSIG . 3000 PSIG +/- 120 PSI 3 PI-0105C 1% cs. 25 PSI 3000 PSIG 3000 PSIG +/- 120 PSI 3 PI-0104 0.5% cs ol 3000 PSIG 3000 PSIG +/- 91 PSI 4 SMM-0114 8.5 PSI 4 . ol 3000 PSIG 3000 PSIG +/- 91 PSI 11 4 PT-0105B CONT PI-0105B 1% cs 25 PSI 3000 PSIG 3000 PSIG +/- 120 PSI 5 PI-01050 1% cs 25 PSI 3000 PSIG 3000 PSIG +/- 120 PSI 5 SMM-0124 8.5 PSI 4 ol 3000 PSIG 3000 PSIG +/- 91 PSI 11 5 PT-0751A3 . CONT PIC-0151A 1% cs 10 PSI 1000 PSIG 1000 PSIG +/- 90 PSI 6 6 PT-1805A 590 HALL LPIR-0382 0.5C cs 1 PSI 300 PSIA 200 PSIA +/- 3 PSI 7 7 PT-1812A ccw LPIR-0383 0.5% cs 1 PSI 300 PSIA 200 PSIA +/- 3 PSI 8 8 LT-0103 CONT Ll-0103A 1% cs 1% 288% 100% +/- 18% 9 Ll-0103B 1% cs. 1% 288% 100% +/- 18% . 9 9 PT-18142 CCW RM 123 PIA-1814 0.5% cs 0.05 PSI 5 PSIG 5 PSIG +/- .09 PSIG 10 PT-18152 CCW RM 118 PIA-1815 0.5% cs 0.05 PSI 5 PSIG 5 PSIG +/- .09 PSIG 10 Notes:
- 1. Digital meter has ze.ro readability error.
- 2. This transmitter is a Fisher-Porter. not Rosemount. Use of Rosemount based errors is expected to bound those for F&P. since errors are very conservatively calculated and applied to Palisades *.
- 3. This calculation applies to PT-07518-0 and PT-0752A-O.
- 4. Accuracy frOlll Technical Specification Surveillance Procedure RI-69 (Reference 5).
MI1188-1661A-TC01
@ consumers Power
- company NUCLEAR OPERATIONS DEPARTMENT Analysis Continuation Sheet EA - RJC-88-01 Sheet 5 of 7
&.cv.-o-Calculation 1 PT-0104 and PI-0104A ERCVR = +/- .5% CS EREAD =0 EL =+/- [.Jf .025 (3000) + .005 (600)] 2 + [.005 (600)) 2 +OJ EL = +/- 78 PSI Calculation 2. PT-01048 .and PTR-0125 ERCVR = +/- 1% CS EREAD = +/- 5 PSI EL = +/-. [..j[.025 (3000) + .005 (600)) 2 + [.01 (600)] 2 + 5J EL = +/- 83.3 PSI, round to +/- 84 PSI Calculation 3 PT-0105A and PI-0105A PT-0105A and PI-0105C ERCVR = +/- 1% CS EREAD = +/- 25 PSI
. EL = +/- [..j[.025 (3000) + .005 (3000)]z + [.Ol (3000)) 2 + 25J EL = +/- 119.9 PSI, round to +/- 120 PSI Calculation 4 PT-0105A and PI-0104 ERCVR = +/- .5% CS EREAD = +/- 0 EL = t [..j[.025 (3000) + .005 .(3000))2 + [.005 (600))2 +OJ EL = t 90.1 PSI, round to +/- 91 PSI
@ consumers Power company NUCLEAR OPERATIONS DEPARTMENT Analysis Continuation Sheet EA - RJC-88-01 Sheet 6 of 7
---;;J.0-Calculation 5 PT~Ol058 and PI-01058 PT-01058 and PI-01050 ERCVR = +/- 1% CS EREAO = +/- 25 PSI EL = +/--[~[.025 (3000) + .005 (3000)) 2 + [.01 (3000)) 2 + 25)
EL = +/- 119.9 PSI, round to +/- 120 PSI Calculation 6 PT-0751A and PIC-0751A ERCVR = +/- 1% CS EREAD = +/- 10 PSI
.EL = +/- [~(.045 (1000) + .035 (1000)] 2 + [.01 (1000)) 2 + 10)
EL : :; +/- 90 PSI Calculation 7 PT-1805A and LPIR-0382 ERCVR = +/- .5% CS EREAD = +/- 1 PSI ExMTR = +/- .25% CS EL = +/- [~[.0025 (200)) 2 + [.005 (200)]2 + 1)
EL = +/- 2.1 PSI, round to+/- 3 PSI Calculation 8 PT-1812A and LPIR-0383 ERCVR = +/- .5% CS EREAD = +/- 1 PSI EXMTR = .25% CS Et = z [~( .0025 (200) I 2 + [ .005 (200) p + 1]
.EL = +/- 2.1 PSi, round to.+/- 3 PSI
@ consumers Power company NUCLEAR OPERATIONS DEPARTMENT Analysis Continuation Sheet
.EA - RJC-88-01 Sheet 7 of _7_.
cl/. o Calculation 9 LT-0103A and LI-OlO~A LT-0103A and LI-01038 ERCVR = +/- U: CS EREAD = +/- 1%
EL = +/- [J[.045 (288) + .035 (100)] 2 + [.001 (100)] 2 + 1]
EL = +/- 17. 5%, round to +/- 18%
Calculation 10 PT-1814 and PIA-1814 PT-1815 and PIA-1815 '
ERCVR = +/- .0.5% CS EREAD = +/- 0.05 PSI ExMTR = +/- 0.5% CS EL *_= +/- !J[.005 (5)] 2 + [.005 (5)] 2 + .05]
EL = +/- .085 PSI, round to+/- .09 PSI Calculation 11 PT-0105A and SMM-0114 PT-01058 and*SMM-0124
- ERCVR = +/- 8.5 PSI EREAD = 0 .
EL = +/- !J[.025 (3000) + .005 (3000)] 2 + 8.5 2 EL = +/- 90.4 PSI, round to +/- 91 PSI MI1188-1661A-TC01
