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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212G1611999-09-22022 September 1999 Proposed Tech Specs,Requesting one-time Extension of Unit 2 Surveillance Interval for Snubber Functional Testing ML20212F6611999-09-20020 September 1999 Proposed Tech Specs,Revising Surveillance Std to Which Ventilation Charcoal Must Be Laboratory Tested as Recommended by GL 99-02 ML20210B8771999-07-15015 July 1999 Final,Typed TS (Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by ML20210B8981999-07-15015 July 1999 Final Typed Pages for LARs 109 & 115,previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115 ML20210B8401999-07-15015 July 1999 Proposed Tech Specs Revising Surveillance Frequency for Quench & Recirculation Spray Systems Nozzle Air Flow Test from 5 Years to 10 Years,Per Guidance Provided in GL 93-05 ML20209C1941999-06-28028 June 1999 Typed,Final TS Pages for LAR 115.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196G3871999-06-22022 June 1999 Proposed Final Tech Spec Pages for LARs 259 & 131 ML20196F0191999-06-17017 June 1999 Proposed Tech Specs Pages for LARs 262 & 135 ML20196F6881999-06-17017 June 1999 Proposed Tech Specs Updating Heatup,Cooldown & Overpressure Protection Curves & Bases to Apply for Up to 15 EFPYs ML20195K1821999-06-15015 June 1999 Proposed Tech Specs Pages for LAR 109 Re RCS ML20207E1851999-05-27027 May 1999 Proposed Tech Specs,Revising Frequency Notation for Manual Functions Specified in ESFAS to More Clearly Denote Appropriate Refueling Frequency for Testing ML20207E2331999-05-27027 May 1999 Proposed Tech Specs 3/4.3.3.3,relocating Seismic Instrumentation Requirements to Licensing Requirements Manual Based on Guidance Provided in GL 95-10 ML20207E2081999-05-27027 May 1999 Proposed Revised Tech Specs for LARs 259 & 131,revising Qualifications for Operations Mgt & Incorporating Generic Position Titles ML20205H5121999-03-31031 March 1999 Proposed Tech Specs Changes to Index Page Xvii,Changing Wording of Title for Table 3.7-1.Table 3.7-2 Will Be Changed to Be Consistent with Title of Table 3.7-3 ML20211N6651999-03-25025 March 1999 Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing (IST) Program for Pumps & Valves ML20204E4381999-03-16016 March 1999 Proposed Tech Specs Bases Section 3/4.7.13,adding Wording Which Discusses Design Bases of Sys in Greater Depth ML20204E3851999-03-16016 March 1999 Proposed Tech Specs LCO 3.7.1.3,increasing Min Vol in Primary Plant DW to 127,500 Gallons,Adding New Footnote & Revising Wording Contained Action Statements ML20207K1331999-03-0303 March 1999 Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207E6261999-02-26026 February 1999 Proposed Typed,Final Tech Specs Pages for LAR 111 ML20199G5431999-01-18018 January 1999 Proposed Tech Specs Re Limiting Safety Sys Settings 2.2.1 & Associated Table 2.2-1 ML20198F9661998-12-24024 December 1998 Proposed Tech Specs Section 3/4.8.1, AC Sources, Clarifying EDG Fuel Oil Storage Requirements by Addition of Term Usable & Increasing EDG Largest Single Load Rejection Test Requirements ML20206N9541998-12-24024 December 1998 Proposed Tech Specs,Modifying Applicable Sections by Removing Rod Position Deviation Monitor,Rod Insertion Limit Monitor,Afd Monitor & QPTR Monitor ML20198D6711998-12-14014 December 1998 Proposed Typed,Final Tech Specs Pages for LARs 246 & 116, Consisting of Editorial Changes Due to Pagination,Changes Incorporated by Previous Amends & Corrected Typos ML20205F6961998-11-30030 November 1998 Revs to Offsite Dose Calculation Manual ML20211K6871998-11-30030 November 1998 Issue 2,Rev 1 to Inservice Testing (IST) Program for Pumps & Valves ML20155J0161998-11-0303 November 1998 Proposed Tech Specs Page 3/4 1-15,re Reactivity Control Sys ML20155B9681998-10-23023 October 1998 Proposed Final,Typed Tech Specs Bases Pages for LARs 260 & 133 Re Limiting Safety Sys Settings ML20154Q8021998-10-15015 October 1998 Proposed Tech Specs,Deleting Two License Requirements, Modifying One LCO Applicability,Modifying Three Definitions, Changing Action Statement Number & Deleting Meteorological Monitoring Spec ML20154Q4341998-10-15015 October 1998 Proposed Tech Specs,Adding Discussion That Explains Why Use of Time Constants,Expressed as Equality,Such as T = X Seconds,Are Acceptable ML20154D6381998-09-30030 September 1998 Proposed Tech Specs Re Revised Typed Bases for LAR 235 ML20154C6501998-09-24024 September 1998 Proposed Tech Specs Section 3.1.2.8,eliminating Potential for non-conservative Interpretation of Values of RWST & Bat Min Contained Volume & Eliminating Need for Plant Administrative Controls ML20197C5711998-09-0808 September 1998 Proposed Typed,Final TS Pages Re Surveillance Requirements for LAR 235 ML20154D5241998-08-14014 August 1998 Issue 2,Rev 0C to Inservice Testing (IST) Program for Pumps & Valves ML20202G9831998-07-22022 July 1998 Issue 3,rev 2 to BVPS Unit 1 IST Program for Pumps & Valves ML20236S4921998-07-15015 July 1998 Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation ML20236S2881998-07-13013 July 1998 Proposed Tech Specs Revising BVPS-1 UFSAR Pages 9.7-7 & 8 & BVPS-2 UFSAR Pages 3.6-11 & 12 Re Potential Flooding of Intake Structure Pump Cubicles ML20236P8051998-07-0909 July 1998 Proposed Tech Specs Revising TS 3.7.1.1, Svs, Incorporating Improved STS Guidance of NUREG-1431 & Recommendations of W Nuclear Safety Advisory 94-01,dtd 940120 ML20236P7761998-07-0909 July 1998 Proposed Tech Specs 3/4 3-2,3/4 3-11 & B 3/4 3-1b,modifying Source Range Neutron Flux Requirements to Allow Use of Alternate Detectors ML20249C4531998-06-23023 June 1998 Final Tech Specs Pages for LARs 256/126 ML20249C3161998-06-19019 June 1998 Proposed Tech Specs Modifying Channel Calibr Definition to Exclude RTDs & Thermocouples from TS Channel Calibr Requirements ML20248M1901998-05-19019 May 1998 Proposed Rev 2F to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves ML20247L3071998-05-14014 May 1998 Proposed Tech Specs,Final Pages for License Amend Requests 249/118 & 254/123,as Amends A-249,A-118,A-254 & A-123, Respectively ML20247J2851998-04-20020 April 1998 Alternative Request BV1-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (RC-R-1-C-8) ML20247J6761998-04-20020 April 1998 Alternative Request BV2-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (2RCS-REV21-C-4) ML20216J9771998-04-13013 April 1998 BVPS Unit 1,Cycle 13 Startup Physics Test Rept ML20248K3061998-03-20020 March 1998 Rev 1,Issue 3 to Inservice Testing Program for Pumps & Valves ML20237B9721998-03-19019 March 1998 Rev 1 to Procedure Npdap 2.14, Fitness-For-Duty for Duquesne Light Employees ML20216G7011998-03-17017 March 1998 Proposed Tech Specs,Revising Engineered Safety Feature Actuation Sys Instrumentation Table 3.3-3,action 34 & Associated Bases Section ML20216G1011998-03-16016 March 1998 Proposed Tech Specs Adding New LCO 3.0.6 to Section 3/4.0, Applicability ML20216G0801998-03-16016 March 1998 Proposed Tech Specs,Exempting Neutron Flux Detectors from Channel Calibr Requirements 1999-09-22
[Table view] Category:TEST REPORT
MONTHYEARML20216J9771998-04-13013 April 1998 BVPS Unit 1,Cycle 13 Startup Physics Test Rept ML20137T3441997-04-0909 April 1997 Cycle 7 Startup Physics Test Rept ML20117B7151996-08-15015 August 1996 Cycle 12 Startup Physics Test Rept ML20087G8811995-08-0808 August 1995 Cycle 6 Startup Physics Test Rept ML20084U7261995-06-0606 June 1995 Cycle 11 Startup Physics Test Rept ML20064H3711994-03-0909 March 1994 Cycle 5 Startup Physics Test Rept ML20063H7491994-01-24024 January 1994 Reactor Containment Bldg Integrated Leakage Rate Test Rept for 1993 for Beaver Valley Power Station Unit 2 ML20056F7501993-08-10010 August 1993 Reactor Containment Bldg Ilrt,Beaver Valley Power Station, Unit 1,May 1993 ML20086A5701991-11-0505 November 1991 Cycle 9 Startup Physics Test Rept ML20067E4401991-01-17017 January 1991 Startup Physics Test Rept, Re Verifying Adequacy of Cycle 3 Reload Core Design.Each Test Performed Indicated Measured Parameters Which Were within Specified Acceptance Criteria ML20029A1361990-11-30030 November 1990 Reactor Containment Bldg Integrated Leakage Rate Test. ML20086S9581990-10-31031 October 1990 Issue 1,Rev 1,to SI Accumulator Discharge Check Valve Full Stroke Test, Test Results Rept ML20012C4671990-03-0505 March 1990 Reactor Containment Bldg Integrated Leak Rate Test. W/ 900309 Ltr ML20086S9391989-12-13013 December 1989 Issue 1,Rev 1,to SI Accumulator Discharge Check Valves Full Stroke Test, Test Results Rept ML20245H7821989-08-0404 August 1989 Startup Rept Suppl 6 ML20248A7771989-06-30030 June 1989 Cycle 2 Startup Physics Test Rept ML20246M2901989-05-0404 May 1989 Suppl 5 to Startup Rept ML20247D9051989-03-20020 March 1989 Initial Startup Test Deferral Rept for First Refueling ML20235N0891989-02-0303 February 1989 Startup Rept Suppl 4 for Beaver Valley Power Station, Unit 2 ML20206E7571988-11-10010 November 1988 Startup Rept,Suppl 3 ML20065G8671988-08-26026 August 1988 Reported Turbine Component Damage at Beaver Valley Power Station Unit 1 Re Conduct of Operational Surveillance Test (Ost) 1.23.1 ML20151T5481988-08-0202 August 1988 Startup Rept,Suppl 2 ML20154A0801988-05-0202 May 1988 Startup Rept Suppl 1 ML20246H9871988-04-30030 April 1988 Environ Qualification of Continental Wire & Cable Corp Instrumentation Cable Installed in Beaver Valley Power Station Unit 1 ML20245D4371988-03-31031 March 1988 Cycle 7 Startup Physics Test Rept ML20148F7131988-03-0404 March 1988 Reactor Containment Bldg Local Leak Rate Test ML20214F3471987-05-0808 May 1987 Reactor Containment Bldg Ilrt,Types A,B & C Preoperational Test ML20214U3341986-09-30030 September 1986 Cycle 6 Startup Physics Test Rept ML20215K6471986-08-31031 August 1986 Reactor Containment Integrated Leakage Rate Test Results Rept, Jul-Aug 1986 ML20129G8141985-06-0404 June 1985 Test Rept on Electrical Separation Verification Test for Duquesne Light Co Beaver Valley Power Station,Unit 2 ML20112C6481985-01-31031 January 1985 Cycle 5 Startup Physics Test Rept ML20112A5641984-12-31031 December 1984 Local Leak Rate Test,Type B & C ML20093J0941984-03-26026 March 1984 Revised Testing of Dissolved Oxygen Analyzers for Post-Accident Analysis Application ML20093J0911984-02-0707 February 1984 Testing of L&W 7075-3 Ph Receiver & Electrode Preamplifier & Meridian Ph Electrode for Pass Applications ML20082N9741983-09-30030 September 1983 Reactor Containment Bldg Integrated Leak Rate Test,Types B & C ML20083H4411983-09-30030 September 1983 Cycle 4 Startup Physics Test Rept ML20095F0251983-08-31031 August 1983 Experimental Evaluation of Reactor Containment Sump ML20063P8071982-10-0505 October 1982 Cycle 3 Startup Test Rept ML20063A0501982-05-31031 May 1982 Reactor Containment Integrated Leakage Rate Test Results Rept,1982 ML20138N7081981-12-24024 December 1981 Test Program to Evaluate DBA Performance of Overlaps Coating Sys (Carboline/Imperial) for Beaver Valley Unit 2 ML20004E5041981-02-28028 February 1981 Cycle 2 Startup Test Rept. ML19316A7281980-03-25025 March 1980 Test Rept for Environ Qualification Test of Penn Union & Marathon Terminal Blocks. ML19242D3661979-08-10010 August 1979 to 1978 Reactor Containment Integrated Leak Rate Test Rept.Revision Includes More Detailed Info Concerning Containment Air Lock Leak Testing & Date Correction Re Performance of Type B Leak Tests ML19246B9101979-02-26026 February 1979 Installation Test Rept for Kinemetrics Sma,S/N 170 Recording Sys W/Three Teledyne FB-103B Accelerometers,One Teledyne 36180 Trigger & Kinemetrics SMP-1,S/N 181 (Playback Unit). 1998-04-13
[Table view] |
Text
. . DUQUESNE' LIGHT COMPANY BEAVER VALLEY POWER STATION UNIT 1 CYCLE 6' STARTUP PHYSICS TEST REPORT September, 1986
- i Prepared by: [.[ d, A. R. Burg Core Performance Engineer Reviewed by:
v A////,,;4 Approved by: -
,h h R. J. Druga T. D. Jones Acting Plant Manager General Manager Nuclear Operations 8612090231 a61120 4 DR ADOCK 0500
BEAVER VALLEY POWER STATION Cycle 6 Startup Test Report INTRODUCTION:
This report describes the startup tes t program applicable for the Cycle 6 reload core design verification for Beaver Valley Power Station, Unit 1. This tes ting program consisted of the following measurements conducted from August 18, 1986 through September 8,1986:
- 1. Control rod drop time measurements
- 2. Initial criticality
- 3. Critical boron concentration measurements
- 4. Control bank worth measurements
- 5. Temperature coefficient measurements
- 6. Reactivity computer checks
- 7. 30% power symmetry check
- 8. Incore/Excore cross-calibration
- 9. Power distribution measurements at 75% and 100% power The results of these startup tests are summarized in this report and comparisons are made to predicted design values and applicable BVPS Technical Specification Requirements.
Beaver Valley Power Station Cycle 6 Startup Test Report Page 2 TEST SUMMARIES:
BVT 1.1 - 1.1.1 " Control Rod Drop Time Measurements" PURPOSE:
The purpose of this test was to determine a drop time for each full-length Rod Cluster Assembly with the RCS in Hot Standby, Tavg > 541* F, and full RCS fl ow.
TEST DESCRIPTION:
A single RCCA Bank is withdrawn to the full-out position (228 steps). A visicorder is connected to the detector primary coil and test leads are then inserted at the stationary gripper coil jacks in the power cabinets. The RCCA blown fuse indicator and moving coil fuse are removed. After the visicorder is turned ON, an assembly is dropped by pulling the stationary gripper fuse out.
Each of the 48 rod cluster assemblies is tested in this manner and the drop times are determined from the visicorder traces. .
RESULTS :
The test was started at 0555 on August 18, 1986 and completed at 1759 on Augus t 18, 1986. The drop times of all 48 rods were well within the BVPS Technical Speci fica tion Requi rement of < 2.2 seconds, with the slowest time being 1.37 seconds for rods K-14, B-6, and F-8 at hot full RCS flow.
Beaver Valley Power Station Cycle 6 Startup Test Report Page 3 BVT 1.6 - 2.2.1 " Initial Approach to Criticality" PURPOSE:
The purpose of this test was to (1) achieve initial criticality; (2) determine the point at which nuclear heat occurs and establish the zero power physics testing decade; (3) verify the proper calibration of the reactivity computer.
TEST DESCRIPTION:
Ini tial conditions were established with the shutdown banks fully withdrawn, control banks fully inserted, boron concentration 1943 ppm, RCS temperature at ~
547 *F and RCS pressure at 2235 psig on August 24, 1986 at 0840.
The control ba nks were withdrawn in 50 step intervals until Control Bank D reached 160 steps. An inverse count rate ratio (ICRR) was taken at each interval. During control rod withdrawal, the ICRR dropped from 1.0 to approximately 0.42.
Dilution to criticality was then commenced at 1005 at a rate of approximately 1000 pcm/hr. Again, ICRR was monitored and plotted at 20 minute intervals. At 1415 on August 24, 1986 af ter 12,923 gallons had been added criticality was achi ev ed.
Following the recording of criticality data at g440, power was increased toward nuclear heat. Nuclear heat occurred at 7 x 10 - amps as indicated on the Th reactivit4 2.9 x 10- computer. amps to 7 x on amps 10-g thezero power reactivity physics testing band (ZPPTB) was computer.
A reactivity computer operational checkout was then performed using the reactor with positive reactivity insertions of 25 pcm, 34 pcm , and 56 pcm. The doubling times were measured and predicted reactivity compared to measured for each insertion. BVT 1.6-2.2.1 was completed at 1955 on August 24, 1986.
RESULTS:
The all rods out ( AR0) critical boron concentration corrected for rod position was calculated to be 1538 ppm with an acceptance criteria of 1504 +~ 50 ppm.
Thus, the inferred value was within the acceptance criteria.
The ZPPTB was set at 2.9 x 10-9 amps to 7 x 10-8 amps based on a measured nuclear heating point of 7 x 10-7 amps and background reading of 2.9 x 10-10 amps.
All the test runs fo r the reactiv i ty computer were within the acceptance criteria of 4%. The errors for the three test cases were 0.60%, 2.35% and 2.30%
'. Beaver Valley Power Station Cycle 6 Startup Test Report
. Page 4 BVT 1.6-2.2.2 " Core Design Check Test" PURPOSE:
The purpose of this test was to verify the reactor core design data between 0 and 100 percent power, and to perform the incore/excore cross-calibration prior to exceeding 75% reactor power.
TEST DESCRIPTION:
The test was divided into five parts: -
Section A cov ered zero power physics tes ts. These tests included boron endpoint measurements, boron dilution worth measurement of the reference bank (CBB), rod .=wsp ba nk worths, di f ferential L,oron worth, and a isothermal temperature coefficient measurement.
Section B involved verifying core symmetry by performing a full-core flux map prior to exceeding 30% reactor power.
Section C requi red incore/excore calibration prior to exceeding 75% of rated thermal power. This involved performing BVT 1.3-2.2.3, " Nuclear Power Range Cal i b ra t io n" , in which a series of flux maps are run at various axial offsets.
Section D required a full-core flux map to be obtained between 40% and 75%
reactor power to ensure that the measured peaking factors were within their applicable Technical Specification limits.
Finally, Section E involved perfonning a full-core flux map at 100% reactor power. This map served as a celibration check for the incore/excore calibration and veri fied that the power distribution limits of the Technical Specifications were not exceeded.
RESULTS:
Boron Endpoint:
The all rods out ( AR0) critical boron concentration was measured to be 1526.6 ppm at 2241 on August 24, 1986. This val ue was within the acceptance criteria of 1504150 ppm.
The Control Bank B-in cri tical boron concentration was measured to be 1373.3 ppm at 0532 on August 25, 1986. This value was within the acceptance criteria of 1325 ppm _t 15%.
Beaver Valley Power Station j
- Cycle 6 Startup Test Report i Page 5 l Temperature Coefficients The isothermal tempe rature coefficient (ITC) was measured at AR0, HZP conditions on August 24, 1986 at 2354. The average measured ITC was detennined to be -2.96 pcm/* F which was within the acceptance cri teria of -2.59 + 3 pcm/* F. Subtracting out the predicted design v al ue of the dopple r coef ficient (-2.12 pcm/
- F) from the measured ITC, the MTC was calculated to be -0.84 pcm/
- F. This value for the MTC meets the requirements of BVPS Technical Specifications which require the MTC to be between -50 pcm/ F and 0 pcm/* F.
Dif ferential Boron Worth The measured di f fe rential boron worth was 8.15 pcm/ ppm. This value was within the acceptance criteria of 7.54 pcm/ ppm + 15%.
RCC Bank Worths The boron dilution measurement of the reference bank for rod swap, CBB was completed at 0352 on August 25, 1986. Following the insertion of CBB, the worths of the remaining control and shutdown banks were obtained relative to CBB on August 25, 1986, between 0726 and 0932. The measured worth, predicted value, and percent difference for each RCC bank and total RCC worth are listed in Table I. All the measured values were within the acceptance criteria for this test.
Reactivity Computer The reactiv ity computer was checked prior to low power physics testing (LPPT), every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during testing, and at the conclusion of LPPT using the exponential generato r. In addition, the reactivity cortputer was checked with the reactor following initial criticality. In all ca ses the computer error was within the 4% acceptance criteria, with the highest measured error being 2.35%.
30 Percent Power Symmetry Check A full-core flux map was performed on August 28, 1986 at approximately 30%
power with CBD at 178 steps to determine the initial flux distribution in the core. Table II lists the values measured for cuadrant power tilt, nuclear enthalpy hot channel factor (F N ), and maximum deviation from predicted relative assembly powers. AH A slight core tilt was measured during this map, however a full-core flux map had already been scheduled for 75% power. All other values were within the acceptance cri teria and applicable Technical Specifications, thus it was decided to recheck the core tilt during the 75% flux map.
r Beaver Valley Power Station Cycle 6 Startup Test Report Page 6 75 Percent Power Flux Map and Incore/Excore Calibration On August 31, 1986 and September 1,1986, BVT 1.3-2.2.3, " Nuclear Power Range Calibration", was performed (at 75% power). This test involved a full-core and six quarter-core flux maps performed at various axial offsets to calibrate the excore detectors and verify core peaking facto rs. The results from these maps were all well within the applicable Technical Specifications as illustrated in Table II.
100 Percent Power Flux Map A full-core flux map was performed at 100% power on September 8,1986.
This map served as a check for the incore/excore calibration saa power distribution limits. Again, all measured peaking factors were within the BVPS Technical Specifications as Table 11 snows.
This 100% flux map marked the completion of the reload startup test program for Beaver Valley Power Station, Unit I, Cycle 6.
Beaver Valley Power Station
. Cycle 6 Startup Test Report Page 7 TABLE I CONTROL R0D BANK WORTHS Control Measured Predicted Error Acceptance Bank Value (pcm) Value (pcm) (%) Criteria CBB* 1249.0 1349 -7.41 110%
CBD 1072.2 1154 -7.09 il5%
CBC 797.6 833 -4.25 15%
CBA 596.1 624 -4.47 115%
SBB 963.7 1014 -4.96 il5%
SBA 1006.3 1080 -6.82 - 115%
TOTAL WORTH 5684.9 6054 -6.10 10%
l
_b
- Beaver Valley Power Station Cycle 6 Startup Test Report Page 8 e
TABLE II ,
FULL CORE FLUX MAPS 4
30% Power 75% Power 100% Power CBD = 178 steps CBD = 193 steps AR0 Acceptance Criteria Quadrant Tilt 1.0210 1.0149 1.0121 11.02 For power ,
above 50%
Maximum Deviation 4.8% 4.5% 3.2% t 10% of Predicted for from Predicted Relative Power > .9 Assembly Powers t
Tech. Spec. :
< 1.87 for 30%
FN 1.4670 < 1.67 for 75%
~
All 1.5680 1.4968
< 1.55 for 100%
Tech. Spec.:
<4.6168 for 30%
F 1.8526 < 3.1152 for 75%
Q 2.1348 1.9604
< 2.3154 for 100%
8 I
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