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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
[Table view] Category:TEST REPORT
MONTHYEARML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17306A5911991-12-31031 December 1991 Reactor Containment Bldg 1991 Integrated Leak Rate Test Final rept.W/920319 Ltr ML17305B1921990-11-13013 November 1990 Piping Verification Test Summary. W/901113 Ltr ML17305A8411990-02-28028 February 1990 1990 Reactor Containment Bldg Integrated Leak Rate Test Final Rept. ML17304A6291988-10-31031 October 1988 Startup Rept,Suppl 1. ML17304A2551988-07-31031 July 1988 Suppl 1 to Palo Verde Nuclear Generating Station Unit 3 Startup Rept. ML20150E6711988-02-29029 February 1988 Vols I-III of Reciprocating Charging Pump Test Rept ML20155A9331987-12-24024 December 1987 Analysis of Reactor Coolant Pump Shaft W/Modified Key Region ML17303A4551987-07-0101 July 1987 Piping Verification Program,Test Summary. W/870701 Ltr ML17300A9181987-06-30030 June 1987 Suppl 2 to Palo Verde Generating Station Unit 2 Startup Rept. ML20207R9931987-03-31031 March 1987 Suppl 1 to Palo Verde Nuclear Generating Station Unit 2 Startup Rept ML20207N0531986-12-31031 December 1986 Rev 0 to Palo Verde Nuclear Generating Station,Unit 2 Startup Rept ML17303A1811986-12-0101 December 1986 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. W/861208 Ltr ML20214T8891986-11-30030 November 1986 Suppl 3 to Startup Rept ML20214L8401986-08-31031 August 1986 Suppl 2 to Palo Verde Nuclear Generating Station Unit 1 Startup Rept ML17300A2821986-07-15015 July 1986 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. ML20210U6791986-05-31031 May 1986 Rev 1 to Palo Verde Nuclear Generating Station Unit 1 Startup Rept ML20154D4671986-02-28028 February 1986 Startup Rept ML17299B0511986-02-24024 February 1986 Startup Experience Rept:Mgt Overview. ML20127J4031986-01-20020 January 1986 Safety Equipment Status Sys (Sess) Commissioning Test ML17299A9021985-12-24024 December 1985 Auxiliary Feedwater Pump 48 H Endurance Test Results, Per Sser (NUREG-0857).W/851224 Ltr ML17299A3471985-05-0707 May 1985 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. ML17298B5721984-10-24024 October 1984 Preliminary Prompt Notification Siren Sys Test Rept for 841024 Test. ML20080C5391983-10-15015 October 1983 Preliminary Rev 0 to Pre-Core Emergency & Auxiliary Feedwater Sys Test, Test Results Rept for 830503-0703 ML20080C5601983-10-0505 October 1983 Preliminary Rev 0 to Pre-Core Instrumentation Correlation, Test Results Rept for 830516-0701 ML20080C4511983-09-19019 September 1983 Preliminary Rev 0 to Pre-Core Chemical & Vol Control Sys Integrated Test, Test Results Rept for 830604-0704 ML20080C4341983-09-17017 September 1983 Draft 7 of Preliminary Rev 0 to Pre-Core Turbine Bypass Control Sys Test, Test Results Rept for 830601-0705 ML20080C4211983-09-14014 September 1983 Preliminary Rev 0 to Pre-Core Safety Injection Check Valve Test, Test Results Rept for 830602 ML20080C4781983-09-0707 September 1983 Preliminary Rev 0 to Main Steam Traps & Drain Valves Hot Functional Test, Test Results Rept for 830606-15 ML20080C4671983-08-25025 August 1983 Preliminary Rev 0 to MSIV & Bypass Valves Hot Functional Test, Test Results Rept for 830602-0703 ML20080C4091983-08-25025 August 1983 Preliminary Rev 0 to Atmospheric Dump Valve Hot Functional Test, Test Results Rept for 830603-0822 ML20080C4851983-08-20020 August 1983 Preliminary Rev 0 to Pressurized Performance, Test Results Rept for 830603-17 ML20080C3951983-08-0101 August 1983 Preliminary Rev 1 to Steam Generator Blowdown Sys Test, Test Results Rept for 830611-15 ML20080C5201983-07-27027 July 1983 Preliminary Rev 0 to RCS Expansion Measurements, Test Results Rept for 830411-0715 ML20080C5061983-07-21021 July 1983 Preliminary Rev 0 to Main & Auxiliary Transformer Backfeed, Test Results Rept for 830420-0515 ML20077F4261983-06-30030 June 1983 Rev 0 to Nonproprietary Cycle 1 CPC & Control Element Assembly Calculator Data Base Listing ML20077F4141983-06-30030 June 1983 Rev 1 to Nonproprietary Cpc/Control Element Assembly Calculator Sys Phase II Software Verification Test Rept ML20077F4071983-06-30030 June 1983 Rev 1 to Nonproprietary Cpc/Control Element Assembly Calculator Sys Phase I Software Verification Test Rept ML20080C4931983-06-14014 June 1983 Preliminary Rev 0 to Loose Parts & Vibration Monitoring Sys Hot Functional, Test Results Rept for 830506-0607 ML20080P6441983-02-0909 February 1983 Soil Thermal Property Measurements for Palo Verde Nuclear Plant ML20071E7081983-01-31031 January 1983 Core Protection Calculation & Control Element Assembly Calculator Sys Phase II Software Verification Test Rept. Proprietary Info Deleted ML20071E7001983-01-31031 January 1983 Core Protection Calculation & Control Element Assembly Calculator Sys Phase I Software Verification Test Rept. Proprietary Info Deleted ML17298A5431982-10-22022 October 1982 Failure Analysis of 54-26-1770 Steel Rotor Returned on NPR-97152 from Palo Verde Nuclear Station. ML17300A5321982-09-30030 September 1982 Test Rept on Slender Walls. ML20028G2191981-10-0909 October 1981 Az Nuclear Power Project 150-Inch Reed Switch Position Transmitter & Litton Electrical Connector Seismic Qualification Test (Sine Sweep Testing). Age Considerations for Seismic Design & Surveillance in Mild Environs Encl ML20063A5801981-05-18018 May 1981 Flow Interruption Test for Part 77910,Supplied to C-E ML20009C6991981-05-0808 May 1981 Flow Interruption Test on Gate Valve Assembly. ML20063A6021981-05-0808 May 1981 Corrected Flow Interruption Test on Gate Valve Assembly ML20009C6951981-03-25025 March 1981 Revision a to Flow Interruption Test for Part 77910 Supplied to C-E. ML17300A8201978-08-28028 August 1978 Torsiograph Test Rept of KSV-20-T. 1994-02-24
[Table view] |
Text
ENCLOSURE PALO VERDE NUCLEAR GENERATING STATION UNIT 1 CYCLE 6 STARTUP REPORT 9403080057 940224 PDR ADOCK 05000528 P PDR
4"::-.';"~"":-.'""PvNGs.-'.-:,mI';".>,",'!.!!,". Page 1 of 8
.,': ".'"Uiiit'1-"::Cycle 5!'. $ ,;
.':-.;II:;!':,'Starhip':Repo'it'< .",'q TABLE OF CONTENTS Introduction Low Power Physics Testing Power Ascension Testing.
Cycle 5 Core Load Map.
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'ntroduction The Palo Verde Unit 1 Cycle 5 Core is designed for a burnup of 437 Effective Full Power Days (EFPD). The core loading is detailed in the following table (Core Map on page 8).
Bate Assembly Number of Fuel Rods per Nominal Shims per Average Designation Assemblies Assembly Enrichment Assembly Exposure Gwd/T 168 3.76 G3 48 16 0 52 3.30 168 4.03 G2 24 16 0 62 3.30 180 4.03 Gl 12 52 3.76 0
184 4.03 0 0 52 3.76 172 4.03 F5 32 12 21.786 52 S.60 168 4.03 F4 16 16 21.332 62 3.60 176 8.80 F3 20.907 62 S.60 172 3.80 F2 12 22.172 62 3.60 180 8.80 F1 24 18.647 52 8.60 4.03 FO 0 12,997 3.80 168 4.03 E6 16 32.639 62 3.70 168 3.90 E4 16 16 37.105 62 3.60 168 3.90 E2 16 30.606 62 3.60 168 4.03 El 62 8.90 16 35.106 184 4.03 EO 0 27.667 52 3.90 208 2.78 B1 16 18.462 12 1.92
PVNGS,",,",-;::,,:,':.;;:::,:,:,." Page 3 of 8
"- " '":Unit 1 -.Cycle 5'."',","
"-"'Startup Report '""
The Cycle 5 core makes use of a low-leakage fuel management scheme, in which previously burned assemblies are placed on the core periphery. The majority of the fresh Batch 6 fuel is located throughout the interior of the core where they are mixed with previously burned fuel to minimize power peaking.
Initial criticality for Cycle 5 was declared at 04:04 on November 24, 1993.
Low Power Physics Testing began at 05:00 on November 24, 1998 and ended at 00:57 on November 25,1993. Power Ascension Testing began at 28:85 on November 27, 1993 and concluded at 12:00 on December 5, 1993.
The testing evolution is controlled by two procedures 72PY-9RX01 "Low Power Physics Testing" and 72PA-9ZZ07 "Reload Power Ascension Test."
The tests performed under the control of 72PY-9RX01 are:
AllRods Out (ARO), Hot Zero Power (HZP), Critical Boron Concentration Isothermal Temperature Coefficient Measurement Rod Swap Testing Inverse Boron Worth Measurement.
The tests performed under the control of 72PA-9ZZ07 are:
Radial Power Distribution - 20% Rated Thermal Power (RTP)
Radial Power Distribution - 70% RTP Axial Power Distribution - 70% RTP Radial Power Distribution - 100% RTP Axial Power Distribution - 100% RTP Hot Full Power, ARO, Critical Boron Concentration.
PVNGS. '.-"-'"'"-'..:':; Page 4 of 8 Unit 1'Cycle,5-'-.:':,:."'
Star'tup:Report',"'.';::;,';
Test Criteria The following acceptance criteria apply to each of the tests performed during Low Power Physics Testing and Power Ascension:
Critical Boron Concentration (HZP) g 100 ppm of predicted Isothermal Temperature Coefficient Measurement g 3 pcm/ F of predicted CEA 1bsting Reference Group g 10% of predicted
'II.st Group(s) g 15% or g 100 pcm of predicted
'Ibtal Worth g 10% of predicted Inverse Boron Worth g 15%
Radial Power Distribution - 20% ~ 10% of predicted Radial Power Distribution - 70% g 0.1 RPD units
< 0.05 RMS Peaking Factors - 70% g 10% of predicted Radial Power Distribution - 100% g 0.1 RPD units
< 0.05 RMS Peaking Factors - 100% g 10% of predicted Critical Boron Concentration (HFP) g60 ppm Low Power Physics Vesting AllRods Out (ARO) Critical Boron Concentration (CBC)
This test is performed by obtaining an RCS Boron Sample at equilibrium conditions near ARO (CEA Group 5 -130" W/D) and adjusting this concentration for the reactivity worth of withdrawing Group 6 to ARO.
The measured RCS concentration was 1557ppm which was adjusted to 1558 ppm. The Design HZP ARO CBC is 1656 ppm. This value was within the acceptance criteria.
Isothermal Temperature Coefficient (ITC)
This test is performed by raising and lowering the RCS Temperature and measuring the associated changes with Core Reactivity. The measured ITC with Group 5 at approximately 139" W/D was -1.28 pcm/'F. The prediction forDesign ITC was -1.32 pcm/ F and was corrected to test
.PVNGS ":,-"'::;,':;-~;:;,";:,: Page 5 of 8 Unit 1'ycle 5.;.,: ":
'Startup Rep'oA'!::::
conditions. The corrected Design ITC was -1.37 pcm/ F. The measured ITC met the acceptance criteria and satisfied the surveillance requirement of Technical Specification 4.1.1.8 Rod Worth Measurements The Rod Swap Measurement method was utilized to test the worth of ALL Shutdown and Regulating CEA Groups. The basic technique associated with Rod Swap is measuring one Group through the Boration/
Dilution method (Reference Group) and then swapping it with each of the remaining Groups ('II.'st Groups). The results are summarized in the following table:
Measured Adjusted Measured Design Percent Test Group(s)
Position Position Worth Worth Difference Grp 5, SD 94.00 99.56 -610.8 -578.2 -5.33 A(20)
Grp 2,4 109.50 109.87 -667.7 -647.6 -3.01 D B(9) 109.50 110.24 -670.4 -645.0 -3. 9 SD A(16), SD 114.75 114.60 -692.6 -657.4 -5.09 B(19)
Grp 1 116.25 116.33 -700.8 -666.7 -4.88 SD B(10) 108.25 108.22 -659.1 -647.5 -1.76 D (8) 95.50 95.36 -584.7 -575.5 -1.58 SD B(6) 126,77 126,52 -744.1 -720.2 -8.20 SD A(21) 96.47 95.81 -587.5 -576.0 -1.96 D B(7) 126,02 125.88 -741,6 -720.8 -2.82 eference
-782.5 -778.0 -0,58 Group (Grp 3)
'Ibtal Worth -7441.8 -7212,9 -8.08 Alltest results met the acceptance criteria.
Inverse Boron Worth The Inverse Boron Worth (IBW) is determined by obtaining the measured worth of the CEA Reference Group (Group 3) from Rod Swap Testing and the change in Boron Concentration to get the Reference Group Diluted to the Lower Electrical Limit. The measured IBW was 125.28 ppm/%EX/K The design IBW was 123.8 ppm/%6K/K The acceptance criteria was met.
Page 6 of 8
":"-""Startuy"'Rep'oit'-'i-":
Power Ascension Testing Flux Symmetry Verification - 20% RTP This test is performed by obtaining a flux map from the Fixed Incore Detector System and processing this information with CECOR. The output from CECOR yields a full core map of Relative Power Density.
The maximum deviation obtained was 8.626% and the minimum deviation was'-5.455%. The acceptance criteria for this test was met.
Core Power Distribution Verification - 70% RTP This test is performed by obtaining a flux map from the Fixed Incore Detector System and processing this information with CECOR. The output from CECOR yields a full core map of Relative Power Density.
The maximum deviation obtained was 0.0587. The Root Mean Square (RMS) deviation was -0.0159, Allacceptance criteria for the Radial Power Distribution were met.
The second portion of testing at 70% includes the verification of the Axial Power Distribution. This involves a comparison of the Axial Shape through 51 nodes with predicted, and a RMS evaluation. Both of these measurements were found to exceed the acceptance criteria. The Axial Deviation was -0.1055 (g 0.1) and the RMS was 0.0628 (~0.05). ARer discussions with ABB/CE it was determined that the Predictions provided did not model the End of Cycle (EOC) 4 adequately. At EOC-4 there was an extensive coastdown performed involving both power reductions and temperature reductions. The model used to predict Cycle 5 values did not include this coastdown.
ABB/CE delivered new predictions for 70% RTP and 98% RTP which properly modelled EOC-4. The data collected at 70% RTP was re-evaluated. The maximum deviation on the Axial Power Distribution was
-0.0769 and the RMS was 0.0233. All acceptance criteria for this measurement were met.
Peaking factor comparisons (percent difference from predictions) were as follows: Fzy Oe359%> Fr Oo'208%< Fz Ool10%> and Fq 1o596%o AO parameters met the acceptance criteria.
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.'age Core Power Distribution Verification - 100% RTP 7
This test is performed by obtaining a flux map from the Fixed Incore of 8 Detector System and processing this information with CECOR. The output from CECOR yields a full core map of Relative Power Density.
The maximum deviation obtained was 0.0697 and the minimum deviation was 0.0149. All acceptance criteria for this measurement were met.
The second portion of testing at 98% RTP includes the verification of the Axial Power Distribution. This involves a comparison of the Axial Shape through 51 nodes with predicted, and a Root Mean Square evaluation.
The Axial Deviation was -0.0901 Q 0.1) and the RMS was 0.0315 (g0.05).
All acceptance criteria for this measurement were met.
Peaking factor comparisons (percent difference from predictions) were as follows: F~ -1.147%, Fr -0.072%, F~ 1.746%, and F< -1.231%. All parameters met the acceptance criteria.
Critical Boron Concentration - 100% RTP This test is performed at ARO HFP equilibrium conditions. A RCS Sample is taken and corrected to the nominal conditions which the prediction was calculated. The measured RCS concentration was 1019 ppm which was adjusted to 1013 ppm. The Design HZP ARO CBC was 1052 ppm. The measured value was within the acceptance criteria.
-PVNGS Unit 1 "Cycle 5
SCartup Repor'C
'"'"'age Cycle 5 Core Load Map 8 of 8 T S R P N M L K I H G F E D C B A 241 240 17 PIE420 PIE429 PIE012 PIE003 PIE009 PIE412 PIE427 P2E110 PIE114 PIE018 PIG001 PIF521 PIC111 PIG004 PIE021 PIE107 P2E105 221 220 219 218 217 216 215 214 2D 211 15 PIE209 PI Fill PIG215 PIF119 PIE019 PIC219 PIF122 PIG208 PIF112 PIE210 210 206 208 201 197 196 P2E114 PIG103 PIF401 PIG346 PIF512 PIC327 PIF501 PIC317 PIF416 PIGI06 P2E109 195 194 191 189 188 187 186 183 184 183 182 181 PIEIO9 PIF114 PIC302 PIG340 PIF307 PIG326 PIF517 PIG341 PIF403 PIG214 PIF109 PIE110
~ 180 179 178 PIFA23 PIE001 PIG218 176 174 PIC333 PI F201 PIC322 171 170 169 PIC323 PIF531 PIC330 PIF203 167 166 165 PIC217 PIE022 PIFA15 11 ~ 163 162 161 PIE419 PIC008 PIFI23 PIC321 159 158 PIC311 156 PIC305 154 PIC304 152 151 150 149 147 PIC343 PIF530 PIG314 PI F120 PIC003 PIFA28
~ 146 145 144 143 142 141 140 139 138 137 136 135 D4 133 132 131 PIE024 PIF518 PIC209 PIFSIS PIC328 PIFS32 PIC303 PIF121 PIF124 PIF103 PIC307 PIF520 PIC33S PIF511 PIC211 PIF522
~ 129 128 127 126 PIE014 PIC107 PIE011 PIG331 124 123 PIG318 PIF409 121 120 119 118 117 116 115 PIB122 PIFIOI PIF412 PIG332 PIF308 PIG329 PIEOIS II4 ID
~ 112 111 110 PIEOIO PIF503 PIC221 108 107 106 106 104 103 102 101 100 99 PIG345 PIFS02 PIC316 PIFI06 PIF116 PIF102 PIC301 PIF519 PIG347 PIF514
~ 94 93 91 PIE417 PIC007 PIF118 PIC319 PIFSI3 PIC339 PIF301 PIC310 PIF413 PIC312 PIF302 PIC334 81 PI F105 PIE430
~ 78 77 76 PIE422 PIE017 PIC216
'74 69 PIF202 PIG336 PIF523 PIG324 PIFSIO PIG325 PIF204 PIC337 PIF411 62 PIFA02 61 60 82 51 50 49 48 47 PIE112 PIF113 PIC212 PIC342 PIF516 PIF305 PIC338 PIF504 PIC315 PIF406 PIG206 PIFI07 PIE106 42 41 39 38 37 36 P2E107 PIG108 PIF41S PIC320 PIG344 PIF527 PIC313 PIF410 PIC201 PIRM1 PIC102 P2E112 31 28 27 25 24 21 20 19 PIE211 PIFIIS PIG222 PIF104 PIG213 PIE005 PIG220 PIF117 PIG210 PIF110 PIGIIO PIE208 18 17 16 15 14 13 12 10 9 P2EIII PIE116 PIE020 PIC005 PIF528 PIG112 PIF524 PIG002 PIE016 PIE118 P2E115
'7 6 5 3 2 I PIE421 PIE432 PIE006 PIE013 PIE007 PIE431 PIE418
~ - Neutron Source
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