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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs 1999-09-07
[Table view] Category:TEST REPORT
MONTHYEARML20216G6371997-09-23023 September 1997 ANO Unit 1 SG Tube Exam ML20216H9461997-09-0808 September 1997 Cycle 13 Startup Rept ML20101H8201992-04-30030 April 1992 Reactor Containment Bldg Integrated Leakage Rate Test Rept, for Apr 1992 ML20086J0771991-11-0707 November 1991 Simulator Performance Testing Rept ML20077G9801991-04-30030 April 1991 One,Unit II Reactor Containment Bldg Integrated Leakage Rate Test ML20059E7901990-01-22022 January 1990 ASTM E-72 Load Testing of 2-h Solid Stud Wall ML20247E8271988-11-30030 November 1988 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20155D4931988-05-20020 May 1988 Rev 1 to Reactor Containment Bldg Integrated Leak Rate Test,880501 ML20214K3641986-11-24024 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `B' Pump Case-Surface Flaw ML20214K3951986-11-24024 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `A' Pump Case - Supplementary Topics ML20214K3291986-11-18018 November 1986 Rev 0 to Arkansas Nuclear One,Unit 1 Pump Case - Crack Growth Due to Transients ML20213F4731986-11-0707 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One-1 a Pump Case Indication ML20213F4791986-11-0707 November 1986 Rev 1 to Arkansas Nuclear One-1 Pump Case Stresses ML20214K3161986-11-0707 November 1986 Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `B' Pump Case Indication ML20206T3181986-01-31031 January 1986 Vols I-III of IEEE 634-1978 Std Cable Penetration Fire Stop Qualification Test:Arkansas Nuclear Units 1 & 2, Russellville,Ar - Site Specific,Arkansas Power & Light Co Spec APL-2434, Final Rept ML20203A2311985-10-23023 October 1985 Corrosion Test of Mechanically Sleeved Unit 1 Once-Through Steam Generator Tube ML20099M3031985-01-31031 January 1985 Rev 1 to Nonproprietary Phase I of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Program Test Series Summary Rept ML20215B4391985-01-14014 January 1985 Rev 0 to Pistar Computer Program Verification Document Program Version 3.3.1 ML20112F7681984-12-31031 December 1984 Primary Reactor Containment Integrated Leakage Rate Test, Final Rept ML20128K3561984-12-17017 December 1984 Change Notice 1 to Primary Reactor Containment Integrated Leak Rate Test,Final Rept ML20215B5081984-11-0909 November 1984 Rev 1 to Gensap Program Verification Document Program Version 4.0 ML20096D8011984-08-31031 August 1984 Nonproprietary Final Rept of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Confirmatory Test Program ML20203A1971984-08-0909 August 1984 Rept of Once-Through Steam Generator Mechanical Sleeve 40% Wall Reduction Test 2CAN068408, Unit Two Cycle Four Startup Rept, for Period Ending 8403151984-03-15015 March 1984 Unit Two Cycle Four Startup Rept, for Period Ending 840315 ML20215B5681983-11-19019 November 1983 Computer Program Verification - Stardyne -3 DEC01/82A H Level Ncsi Cyber 730 ML20080T8391983-06-10010 June 1983 Exam of Once-Through Steam Generator Tubes B73-8 & B112-19 from ANO-1, Final Rept ML20071G1921983-05-12012 May 1983 Station,Unit 2,Cycle Three Startup Rept, for Period Ending 830104 ML20072P8111983-03-17017 March 1983 Cycle 2 Refueling Outage Fuel Exam Results ML20215B5451982-11-24024 November 1982 Suppl a to Rev 0 to Gensap Verification. Baseplate II Verification Rept Encl ML20215B5301982-10-23023 October 1982 Rev 0 to Gensap Program Verification ML19350F1251981-06-30030 June 1981 Nonproprietary Version of Reactor Vessel Open Core Flow Model Test Rept. ML19277A0681981-06-16016 June 1981 Nonproprietary Version of Cpc/Ceac Sys Phase II Software Verification Test Rept. ML20009G3181981-06-12012 June 1981 Inservice Testing AND-Unit 1,Check Valve Reliability Analysis. ML20079F9071981-06-0202 June 1981 Nonproprietary ANO-2 Cycle 1 Refueling Outage Fuel Exam Results ML20004C5111981-05-31031 May 1981 B&W Post-Test Evaluation of Loft Test L3-1. ML20004C5161981-05-20020 May 1981 B&W Post-Test Analysis for Semiscale Test S-07-10D. ML20126K9701981-02-25025 February 1981 Primary Reactor Containment Integrated Leakage Rate Test ML20053E9161980-12-12012 December 1980 Rept on Floor & Wall Penetration Fire Stops. ML20003E6161980-10-31031 October 1980 Cesec Simulation of NSSS Transients Tests at AR Nuclear One-Unit 2. ML20151A3841980-07-28028 July 1980 Revision a to Electrical Wire & Cable Isolation Barrier Matls Test for Susquehanna Steam Electric Station,Units 1 & 2 for Bechtel Power Corp ML19323H2841980-04-30030 April 1980 AR Nuclear 1 Steam Electric Station,Unit 2,Startup Rept, Suppl 3 for Period Ending 800430 ML19318C3421980-04-30030 April 1980 Rept on Wall Penetration Fire Stops. ML19344D2581980-01-29029 January 1980 Startup Rept,Suppl 2 for Period Ending 800129. ML19260C3601979-12-17017 December 1979 Pages S1-47,S1-48,S1-A1 & S1-A2 to 791211 Suppl to Startup Rept ML19256G5611979-12-17017 December 1979 Four Pages Omitted from 791211 Submittal of Suppl 1 to 790913 Startup Rept ML19210E2641979-11-29029 November 1979 Revised Pages to Startup Rept Cycle 4 Correcting Error in Moderator Coefficient Extrapolated to 95% Full Power & Indicating Location of in-core Instrumentation Used to Determine Core Power Distribution ML19211A2891979-10-31031 October 1979 Suppl 1 to Startup Rept for Period Ending 791031 ML19209A5141979-09-25025 September 1979 Cycle 4 Startup Rept for Period Ending 790704 ML19208A9361979-07-31031 July 1979 Startup Rept. ML19344A6631979-05-14014 May 1979 Class IE Prequalification Tests for Itt Barton Pressure Differential Switch,Model 580. 1997-09-08
[Table view] |
Text
,
pS o No. b
- y . Report No. R-84-011-NP
<+ ' FINAL REPORT OF THE AP&L ICC MONITORING SYSTEM
.. ' CONFIRMATORY PROGRAM
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AP&L Project Team
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yn ~ ' . Ron Oakley - Project Supervisor Steve Paquette - Project Engineer
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.: 4> - TEC Project Team Wayne Garber, Project Manager
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.l} 4. .; /;/s t Technology for Energy Corporation Q, , One Energy Center, Pellissippi Parkway
-4 M Knoxville, Tennessee 37922 1,, (615) 966-5856
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-August 1984
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, /M F. W. Garbier /- R. A. Hedrick
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E .T-TABLE OF CONTENTS
-Section- Page
- 1. INTRODUCTION 1-1 e
2.- A*R/ WATER TEST _ SERIES 2-1
- .2.1 Overall'0bjectives of the Air / Water Test Series .2-1 2.2 Air / Water Experimental Configuration and Testing Matrix 2.3 Air / Water Results and Conclusions PAGES -
'2.3.1 Results and Conclusions for .
Manometer Port Testing DELETED 2.3.2 Results and Conclusions for AW2100 2.3.3 Results and Conclusions for AW2200 2.3.4 Results and Conclusions for AW2300 2.3.5 Results and Conclusions for AW2400 __ __
- 3. UPPER HEAD TEST SERIES 3-1 3.1 Overall Objectives of the Upper Head Test Series 3-1
~3.2 Upper Head Experimental Configuration and Testing Matrix 3.3 Upper Head Results and Conclusions 3.3.1 Basic Response Patterns During Blowdown 3.3.2 Differential Pressure Transducer pg'GES Comparisons during Blowdown DELETED 3.3.3 Basic Response Patterns During Reflood 3.3.4 Differential Pressure Transducer -,
Comparisons During Reflood ---
4-1
- 4. IN-CORE TEST SERIES 4.1 - Ov erall Objectivs 'f the_In-Core Test Series __ 4-1:.__
4.2 'In-Core Experimental Configuration and Testing Matrix 4.3 In-Core Results and Conclusions 4.3.1 FPS Sheath Thermocouple Comparisons PAGES During' Blowdown 4.3.2 Differential Pressure Transducer Comparisons DELETED During Blowdown 4.3.3 FPS Sheath Thermocouple Comparisons During Reflood 4.3.4 Differential Pressure Transducers Comparisons __ -___
During.Reflood 5-1
- 5. OVERALL. CONCLUSIONS iii
7_.
L. .*
LIST OF TABLES PROPRIETARY INFORMATION PAGE DELETED L'
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LIST OF FIGURES PROPRIETARY INFORMATION PAGE DELETED e
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LIST OF FIGURES-(Continued)
PROPRIETARY INFORMATION PAGE DELETED I
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LIST OF FIGURES (Continued)
PkOPRIETARY INFORMATION PAGE DELETED e-
.- )
l SECTION 1 l INTRODUCTION I
i Arkansas' Power and Light (AP&L) Company has contracted Technalogy for Energy Corporation (TEC) to supply an inadequate core cooling (ICC) system for Arkansas Nuclear One. AP&L and TEC, therefore, designed and conducted an extensive experimental program on the Radcal Inventory Meter (RIM) to verify
. IC capability and to provide licensing support and design data for the
. system hardware. The test program was conducted at facilities leased from the Oak Ridge National Laboratory (ORNL) utilizing two atmospheric air / water test facilities and the pressurized water Forced Convection Test Facility (FCTF). The air / water facilities were used to provide manometer tube design data and basic sensor response parameters. The FCTF is a typical reactor simulation facility that has been used in several Nuclear Regulatory Commission Programs. It has both blowdown and reflood capability with sufficient control and instrumentation systems to perform the tests required to_ simulate a reactor under small break, loss-of-coolant conditions.
The overall objectives of the test program were:
- To verify that the proposed manometer tube design permits unambiguous coolant inventory determinations (above-core),
- To confirm that the RIM probes will detect ICC conditions (above-core and in-core), and #
- To identify the boundary conditions for unambiguous ICC indications (above-core and in-core).
i 1-1
^
V ...
C Section 2 AIR / WATER TEST SERIES
'2.1 OVERALL 0BJECTIVES OF THE AIR / WATER TEST SERIES j The overall objectives of the air / water test series were:
o To provide basic des'ign data on the-manometer tube stilling column and RIM assembly's performance, o To demonstrate that the. final prototype manometer tubes and .
probes can make level measurements in a variety of air / water mixtures and flows, o To obtain basic performance data, response time, and fill and drain rates of the manometer tube-probe assemblies, and e To determine the boundary conditions of flow and void fraction under which the probe assembly can provide unambiguous data to a reactor operator.
DELETED L
- os 2-1
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Section 3
- . UPPER HEAD TEST SERIES 3.1 OVERALL OBJECTIVES 0F THE UPPER HEAD TEST SERIES Th'e overall objectives of the Upper Head Test Series were
o To demonstrate that the prototype inventory meters can supply measurements to provide effective'ICC monitoring of the upper
. . head and upper plenum of the reactor, o To provide data to determine the boundary conditions on unambiguous inventory meter ICC monitoring performance--
depressurization rates.(break size), flow rates (pumps off sensitivity), and refill repressurization, o: To confirm that the absolute temperature measurement provides a good indication of coolant temperature above the core in an ICC event, and o To provide ' data to select the optimum sensor types and arrange-ments in the inventory meter probes for ANO-1 and ANO-2.
i DELETED i
3-1 .l l
(
~^
f' ..-
t*l .s Section 4 IN-CORE TEST SERIES e
4.1 OVERALL OBJECTIVES OF THE IN-CORE TEST SERIES The 'oterall objectives of the in-core test series were:
e e To demonstrate' that the prototype RIM sensors can supply measure-
.ments to provide effective ICC monitoring of the reactor core under low-power conditions; e To provide data to determine the boundary conditions on unambiguous RIM ICC monitoring performance - depressurization rates (break size), flow rates (pumps off sensitivity), and refill repressurization; o To confirm that the absolute temperature measurement provides a good indication of coolant temperature above the core-in an ICC event, and obtain data on how closely the RIM reflects fuel thermal performance; e To provide data to select the optimum sensor types and arrangements in the. RIM probe for ANO-1 and ANO-2.
DELETED l 4-1
)
. 2
1*
.;'l ,.
Y Section 5 OVERALL CONCLUSIONS The breadth of the parameter space in the three test series was significant. Variations in blowdown rate, reflood rate, initial tem-
.f perature, and initial flow were included. Further, three sensor types and three gas-gap length variations within two of the sensor types were tested. The overall conclusions are: ,
- 1. All RIM rods maintained their mechanical integrity, operability, and performance throughout the tests.
- 2. All RIM sensor types respond well to blowdown and reflood transients and could be utilized as ICC warning devices with relatively simple type-specific data processing.
- 3. Inventory loss or gain rate can be determined in addition to i nv entory.
- 4. There is no practical difference in response of RIM rods con-taining different numbers of sensor locations (12- and 16-cable pack designs).
) 5. The response of the sensors is predictable, including variations in absolute temperature and flow.
- 6. Absolute thermocouples in the RIM rods can be used to trend fuel cladding temperature.
- 7. RIM sensors in the instrument guide tube can be used to indi-cate fuel surface conditions.
DELETED s
i 5-1
_