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| Power distribution information was obtained from the computer routine INCA which uses incore detector readings to evaluate power parameters. | | Power distribution information was obtained from the computer routine INCA which uses incore detector readings to evaluate power parameters. |
| The INCA program is routinely run and the computer run chosen for this report was one at 97.5% power and 463.0 MWD/MTU burnup. The information derived from 'l the INCA output consisted of quadrant tilt, assembly power and assembly power RMS deviation. | | The INCA program is routinely run and the computer run chosen for this report was one at 97.5% power and 463.0 MWD/MTU burnup. The information derived from 'l the INCA output consisted of quadrant tilt, assembly power and assembly power RMS deviation. |
| The assembly powers and assembly power RMS were compared to the predicted information supplied bv Exxon in Reference | | The assembly powers and assembly power RMS were compared to the predicted information supplied bv Exxon in Reference |
| : 1. The predicted informa-tion was taken from a PDQ computer run at 100% power and 100 MWD/MTU burnup. Quadrant Tilt The INCA calculated quadrant tilt of 0.31% is well below the review criterion of 3%. Quadrant tilt did not have an acceptance criterion. | | : 1. The predicted informa-tion was taken from a PDQ computer run at 100% power and 100 MWD/MTU burnup. Quadrant Tilt The INCA calculated quadrant tilt of 0.31% is well below the review criterion of 3%. Quadrant tilt did not have an acceptance criterion. |
| Assembly Power PDQ predicted assembly power, measured assembly power, and percent difference between the two are given in Figure 1. The review criterion of +/- 10% was not exceeded. | | Assembly Power PDQ predicted assembly power, measured assembly power, and percent difference between the two are given in Figure 1. The review criterion of +/- 10% was not exceeded. |
| MI1284-0305A-TCOi Assemble Power RMS Deviation power RMS deviation calculated from the assembly powers is also played in Figure 1. The RMS deviation of 3.7% was within the 5% review terion. CONCLUSION 3 Review and acceptance criteria were met for all power distribution parameters. | | MI1284-0305A-TCOi Assemble Power RMS Deviation power RMS deviation calculated from the assembly powers is also played in Figure 1. The RMS deviation of 3.7% was within the 5% review terion. CONCLUSION 3 Review and acceptance criteria were met for all power distribution parameters. |
| This completes the Cycle 6 Start-Up Report. REFERENCES | | This completes the Cycle 6 Start-Up Report. REFERENCES |
| : 1. Palisades Cycle 6 Start-up and Operations Report, XN-NF-83-81, Exxon Nuclear Company, September 1983. 2. Physics Testing Report for Cycle 6 Start-Up, October 1984. | | : 1. Palisades Cycle 6 Start-up and Operations Report, XN-NF-83-81, Exxon Nuclear Company, September 1983. 2. Physics Testing Report for Cycle 6 Start-Up, October 1984. |
| 10 X 10 TO THE INCH* I -. II* INl.tH :, K£Ut-"fEL 6-t0 MAltl IN U-, A I ,. T--lf------* -ir --** *--fT -r*---r I J. I l I *:i 16 IJ 4* D .f i9 -r: .. --* -* .. -: t -. l "' l . *----) I 15 .* .. --*'-.* --1--( --.. -... '---* .. --. --*. -...* -. --L-L----.... -.&.... ** 1-. .. ---. , __ ----.. --L-L-.. '--* -I----1---L-1-L---I--. *. -.. -*. 1-.. -'--. .l---L--.. . '---I I 1 I . *--.. . .. I ' I I . !. 11 _I Ek r r: '--,,)> L 1D <IC -D ( 5 . -D -ID (9 IC 0 IC u K;cl>J pl) | | 10 X 10 TO THE INCH* I -. II* INl.tH :, K£Ut-"fEL 6-t0 MAltl IN U-, A I ,. T--lf------* -ir --** *--fT -r*---r I J. I l I *:i 16 IJ 4* D .f i9 -r: .. --* -* .. -: t -. l "' l . *----) I 15 .* .. --*'-.* --1--( --.. -... '---* .. --. --*. -...* -. --L-L----.... -.&.... ** 1-. .. ---. , __ ----.. --L-L-.. '--* -I----1---L-1-L---I--. *. -.. -*. 1-.. -'--. .l---L--.. . '---I I 1 I . *--.. . .. I ' I I . !. 11 _I Ek r r: '--,,)> L 1D <IC -D ( 5 . -D -ID (9 IC 0 IC u K;cl>J pl) |
Revision as of 22:30, 25 April 2019
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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 REPORT
MONTHYEARML18066A1841998-06-10010 June 1998
Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period.
ML20217C3101998-03-24024 March 1998
Palisades,Review of Actual Fluence Determination
ML18059B0641994-06-13013 June 1994
Simulator Four-Yr Test Rept & Schedule for Performance Testing for Next Four-Yr Period.
ML18057A9241991-02-28028 February 1991
Reactor Containment Bldg Integrated Leak Rate Test, Feb 1991,Special Rept.
ML18054A5321989-02-0303 February 1989
Reactor Containment Bldg Integrated Leak Rate Test,Nov 1988, Special Rept 13
ML18054A5521989-01-31031 January 1989
Cycle 8 Startup Physics Test Rept. W/890217 Ltr
ML18052A3971986-04-30030 April 1986
Special Rept 12, Reactor Containment Bldg Integrated Leak Rate Test,Jan 1986.
ML18051B2811984-12-31031 December 1984
Reactor Internals Noise Monitoring Tests.
ML18051B2331984-12-31031 December 1984
Suppl to Physics Testing Rept for Cycle 6 Startup.
ML18051B1031984-10-31031 October 1984
Physics Testing Rept for Cycle 6 Startup.
ML18051A7921983-12-31031 December 1983
Reactor Internals Noise Monitoring Tests, 1983
ML18051A3021983-01-31031 January 1983
Reactor Internals Noise Monitoring Test, 1982
ML18047A4351982-07-31031 July 1982
Generator Tube Leak Outage Rept of Eddy Current Results.
ML18047A3521982-05-31031 May 1982
Epri/Marshall Electric Motor Operated Valve (Block Valve), Interim Test Data Rept.
ML18047A4611982-04-30030 April 1982
EPRI PWR Safety & Relief Valve Test Program:Safety & Relief Valve Test Rept, Interim Rept
ML18047A2921982-04-14014 April 1982
Physics Testing Rept for Cycle 5 Start-up.
ML18047A3531982-03-31031 March 1982
EPRI Summary Rept:Westinghouse Gate Valve Closure Testing Program, Revision 1
ML18046B3741982-02-28028 February 1982
Reactor Containment Bldg Integrated Leakage Rate Test.
ML18046B3271982-02-24024 February 1982
Reactor Internals Noise Monitoring Tests,Jan-Dec 1981.
ML18046B1591981-12-15015 December 1981
Lab Rept,Battery Section,Ieee 323 Qualification.
ML18046B2061981-12-11011 December 1981
Control Rod Drive Mechanism Dynamic Analysis Rept. Info Re Seismic Analysis of Reactor Internals,Diesel Generator Fuel Oil Day Tanks,Essential Water Svc Pumps Safety Injection Tank & Reactor Coolant Pump Also Encl
ML18046B0801981-10-31031 October 1981
Containment Bldg Post-Accident Sys 10-Yr Surveillance Rept.
ML18046B0841981-07-31031 July 1981
Sheathing Filler Rept.
ML18046A8531981-07-0606 July 1981
Control Rod Drive Mechanism Dynamic Analysis Rept.
ML18045A5481980-07-31031 July 1980
Physics Testing Rept for Core 4 Startup.
ML18045A2931980-07-0101 July 1980
Rept on Endurance Testing of Auxiliary Feedwater Pumps.
ML18044A5391980-02-11011 February 1980
Results of Insp & Testing Program in Response to IE Bulletin 79-02 & Revisions (for Interim Plant Operations) for CPC Facility in South Haven,Mi, Revision 0
ML19296B0471980-02-0808 February 1980
RCS Asymmetric Loads Evaluation Program;Interim Rept.
ML18044A5401980-01-31031 January 1980
Results & Evaluation of Tests on Phillips Red Head Self- Drilling Expansion Anchors for CPC Facility in South Haven, Mi.
ML18045A2221979-11-30030 November 1979
Reactor Internals Noise Monitoring Tests Nov 1978-Nov 1979.
ML18044A3781979-02-28028 February 1979
Rept of Seismic Vibration Testing of Various Electrical Items for B&W Under Purchase Order 033788LG.
ML18043A4901979-01-31031 January 1979
Reactor Internals Noise Monitoring Tests for Period Apr- Oct 1978 (First 6 Full Months of Core 3)
ML18044A3431970-11-30030 November 1970
Containment Bldg Structural Integrity Test.
ML18044A3441970-10-0505 October 1970
Deformation Measurements During Containment Pressure Test.
1998-06-10
[Table view] |
Text
. ,, ** PlfYSICS TESTING REPORT FOR CYCLE 6 START-lTP SUPPLEMENT DECEMBER 1984 p ADOCK 05000255 ---PPR MI1284-0305A-TC01
" . ,, *' 2 *,' INTRODUCTION This report is a supplement to the "Physks Te:s:ti:ng Report for Cycle 6 Start-Up, October 1984." The original report included power distt:ibution informa-tion, but due to several forced outages the highest power level achieved at that point was 79%. This supplementary report presents the result,s of power distribution at essen-tially full power. POWER DISTRIBUTION (SUPPLEMENT)
Power distribution information was obtained from the computer routine INCA which uses incore detector readings to evaluate power parameters.
The INCA program is routinely run and the computer run chosen for this report was one at 97.5% power and 463.0 MWD/MTU burnup. The information derived from 'l the INCA output consisted of quadrant tilt, assembly power and assembly power RMS deviation.
The assembly powers and assembly power RMS were compared to the predicted information supplied bv Exxon in Reference
- 1. The predicted informa-tion was taken from a PDQ computer run at 100% power and 100 MWD/MTU burnup. Quadrant Tilt The INCA calculated quadrant tilt of 0.31% is well below the review criterion of 3%. Quadrant tilt did not have an acceptance criterion.
Assembly Power PDQ predicted assembly power, measured assembly power, and percent difference between the two are given in Figure 1. The review criterion of +/- 10% was not exceeded.
MI1284-0305A-TCOi Assemble Power RMS Deviation power RMS deviation calculated from the assembly powers is also played in Figure 1. The RMS deviation of 3.7% was within the 5% review terion. CONCLUSION 3 Review and acceptance criteria were met for all power distribution parameters.
This completes the Cycle 6 Start-Up Report. REFERENCES
- 1. Palisades Cycle 6 Start-up and Operations Report, XN-NF-83-81, Exxon Nuclear Company, September 1983. 2. Physics Testing Report for Cycle 6 Start-Up, October 1984.
10 X 10 TO THE INCH* I -. II* INl.tH :, K£Ut-"fEL 6-t0 MAltl IN U-, A I ,. T--lf------* -ir --** *--fT -r*---r I J. I l I *:i 16 IJ 4* D .f i9 -r: .. --* -* .. -: t -. l "' l . *----) I 15 .* .. --*'-.* --1--( --.. -... '---* .. --. --*. -...* -. --L-L----.... -.&.... ** 1-. .. ---. , __ ----.. --L-L-.. '--* -I----1---L-1-L---I--. *. -.. -*. 1-.. -'--. .l---L--.. . '---I I 1 I . *--.. . .. I ' I I . !. 11 _I Ek r r: '--,,)> L 1D <IC -D ( 5 . -D -ID (9 IC 0 IC u K;cl>J pl)
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