Technical Description:Reactor Coolant Inventory Tracking Sys (Rcits) Conceptual DesignML20073M984 |
Person / Time |
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Site: |
Crystal River ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
04/15/1983 |
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From: |
FLORIDA POWER CORP. |
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To: |
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Shared Package |
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ML20073M968 |
List: |
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References |
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RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8304220350 |
Download: ML20073M984 (7) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 ML20211L1321999-08-31031 August 1999 EAL Basis Document ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept ML20217B1731998-04-16016 April 1998 FPC Crystal River,Unit 3,Tendon Surveillance Program Engineering Evaluation of Sixth Tendon Surveillance ML20203K1521998-02-28028 February 1998 Post-LOCA Boron Concentration Mgt for CR-3 ML20203K4991998-02-16016 February 1998 Boron Dilution by RCS Hot Leg Injection ML20202J4291998-02-13013 February 1998 Rev 2 to MPR-1887, Crystal River 3 Reactor Bldg Cooling Fan Logic Mod Failure Modes & Effects Analysis ML20198J8181998-01-10010 January 1998 Assessing Performance & Organizational Roles ML20198J8371998-01-10010 January 1998 Engineering ML20198J8621998-01-10010 January 1998 Maintenance ML20198J8821998-01-10010 January 1998 Licensing ML20198J7501998-01-10010 January 1998 Corrective Action Program Overview ML20198J7811998-01-10010 January 1998 Design & Licensing Basis ML20198J8041998-01-10010 January 1998 Integrated Verification Team Rept ML20198J7291998-01-10010 January 1998 Overall Restart Readiness ML20198J8571998-01-10010 January 1998 Operations ML20198J8881998-01-10010 January 1998 Training ML20198H5071997-12-31031 December 1997 Rev 5 to Justification for Continued Operation for CR Emergency Ventilation Sys & Control Complex Habitability Envelope ML20197B2911997-12-11011 December 1997 Generic Operability Evaluation for Large Bore Safety Related Piping at Crystal River-3 ML20198K4451997-11-30030 November 1997 Reactor Bldg Cooling Fan Logic Mod Failure Modes & Effects Analysis, Rev 0 ML20202D4161997-11-26026 November 1997 Mod Outage Integrated Verification Team Rept ML20199K4731997-11-24024 November 1997 Sys Readiness Review Summary Rept ML20212F4191997-10-31031 October 1997 Revised Boron Dilution by RCS Hot Leg Injection ML20199D5751997-10-30030 October 1997 Overview of Safety Related Large Bore Piping & Piping Support Design & Construction Currently Existing at Crystal River-3 Nuclear Power Plant, Rev 0 ML20198T1051997-10-25025 October 1997 Tracer Gas Air Inleakage Measurements within Crystal River Unit 3 Control Complex Habitability Envelope, Summary Rept ML20211N1771997-10-11011 October 1997 Rev 1 to Pressure/Temp Limits Rept ML20210T9421997-08-29029 August 1997 B Dilution by Hot Leg Injection ML20148K7961997-06-12012 June 1997 Safety Analysis Input to Startup Team Safety Assessment Rept ML20148J3821997-05-23023 May 1997 Rev 16 to PSA F Annunciator Response ML20141D9401997-04-16016 April 1997 Summary Document for Pressurizer NDE Development for FPC Crystal River Unit 3 ML20132F4861996-12-0303 December 1996 Restart Panel ML20133B2711996-10-31031 October 1996 Monthly Trend Rept for Oct 1996 ML20199D5431996-10-28028 October 1996 Evaluation of Piping & Support Documentation for Crystal River 3 ML20134K9581996-10-15015 October 1996 Independent Design Review Panel Rept on 961015 ML20117C6431996-07-25025 July 1996 FPC Crngp Unit 3 Graded Approach Methodology for Instrument Uncertainty ML20101F6081996-02-29029 February 1996 Iga & Wear Voltage Correlations & Uncertainty Analysis ML20100G4141996-02-29029 February 1996 Input to Items a & C of NRC Questions on Relief Request for Insp of Transition Piece to Bottom Head Weld at Crystal River Unit 3 ML20100G4281996-02-0101 February 1996 Flaw Acceptance Handbook for Crystal River Unit 3 RPV & Nozzle Weld Insps ML20095L1461996-01-0202 January 1996 Seismic Evaluation Rept for USI A-46, Rev 0 ML20098A4571995-09-19019 September 1995 Plant Ref Simulator Four Yr Simulator Certification Rept ML20101F6001995-06-30030 June 1995 Alternate Disposition Strategy for Low Vol OTSG Eddy Current Indications ML20092M2061995-06-27027 June 1995 Pyrolysis Gas Chromatography Analysis of 3 Thermo-Lag Fire Barrier Samples ML20084L6931995-05-31031 May 1995 Exam of Crystal River-3 Pulled SG Tubes Final Rept B51956, 8R/9R Bobbin Voltage (S/N) Growth Rate Calculations1995-05-31031 May 1995 8R/9R Bobbin Voltage (S/N) Growth Rate Calculations ML20092M2051995-05-11011 May 1995 Pyrolysis Gas Chromatography Analysis of 5 Thermo-Lag Fire Barrier Samples ML20080T4661995-02-27027 February 1995 Final Rept One & Three H Fire Endurance Tests & Hose Stream Tests Thermal Barrier Sys for Electrical Components 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 3F0699-07, Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With ML20210U5601999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Crystal River,Unit 3 ML20195C6271999-05-28028 May 1999 Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates ML20196L2031999-05-19019 May 1999 Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-04, Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With ML20210U5631999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Crystal River,Unit 3 3F0499-04, Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With ML20204D9661999-03-31031 March 1999 Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease1999-03-10010 March 1999 Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease 3F0399-03, Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20206E9891998-12-31031 December 1998 Kissimmee Utility Authority 1998 Annual Rept ML20206E9021998-12-31031 December 1998 Florida Progress Corp 1998 Annual Rept ML20206E9701998-12-31031 December 1998 Ouc 1998 Annual Rept. with Financial Statements from Seminole Electric Cooperative,Inc 3F0199-05, Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With ML20206E9261998-12-31031 December 1998 Gainesville Regional Utilities 1998 Annual Rept 3F1298-13, Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With 3F1198-05, Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20155J2701998-10-28028 October 1998 Second Ten-Year Insp Interval Closeout Summary Rept 3F1098-06, Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With ML20206E9461998-09-30030 September 1998 Utilities Commission City of New Smyrna Beach,Fl Comprehensive Annual Financial Rept Sept 30,1998 & 1997 ML20206E9561998-09-30030 September 1998 City of Ocala Comprehensive Annual Financial Rept for Yr Ended 980930 ML20206E9101998-09-30030 September 1998 City of Bushnell Fl Comprehensive Annual Financial Rept for Fiscal Yr Ended 980930 ML20206E9811998-09-30030 September 1998 City of Tallahassee,Fl Comprehensive Annual Financial Rept for Yr Ended 980930 ML20195E3121998-09-30030 September 1998 Comprehensive Annual Financial Rept for City of Leesburg,Fl Fiscal Yr Ended 980930 3F0998-07, Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document 3F0898-02, Monthly Operating Rept for Jul 1998 for Crystal River,Unit 11998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Crystal River,Unit 1 ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept 3F0798-01, Monthly Operating Rept for June 1998 for Crystal River Unit 31998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Crystal River Unit 3 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History 3F0698-02, Monthly Operating Rept for May 1998 for Crystal River Unit 31998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Crystal River Unit 3 1999-09-30
[Table view] |
Text
ATTACHMENT I TECHNICAL DESCRIPTION REACTOR C00 TANT INVENTORY TRACKING SYSTEM (RCITS)
CONCEPTUAL DESIGN CRYSTAL RIVER - UNIT 3 FLORIDA POWER CORPORATION 8304220350 830415 PDR ADOCK 05000302 P PDR
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SUMMARY
The Reactor Coolant Inventory Tracking System design concept is intended . .
to provide a continuous unambiguous control room indication of reactor vessel head and hot leg coolant inventory trending with reactor coolant pumps (RCPs) either running or tripped. The concept was designed to '
meet the parameters specified in NUREG-0737, item II.F.2. ,
The design concept encompasses the use of dif ferential pressure (DP)'
measurements across vertical elevations of the hot leg and the reactor .
vessel to infer coolant level when the RCPs are tripped, plus the use of RCP motor current measurements and pump inlet temperatures to infer-coolant inventory trends when the RCPs are running. The concept also includes density compensation for DP measurements due to temperature ,
effects on reference leg and process liquid density.
DP measurements cover a wide range measurement from the top to the bottom of the hot leg,-plus a narrow range measurement from the top of %,
the reactor vessel (RV) head to the bottom of the hot leg. A total of four DP transmitters will he used to provide redundancy. - Each pair of wide and narrow range transmitters will be independently powered by Class 1E instrumentation power. They will be mounted within the con-tainment area. Seal chambers will be located at the high point of each reference leg to keep the legs full of water. .
The design concept includes removal of a control. rod drive mechanism to provide a penetration in the RV head for location of the top RV pressure -
tap. The top hot leg pressure tap will be located of f the hot leg high point vent. Florida Power Corporation has already processed and plans to install the lower pressure tap on the decay heat suction line during the 1983 refueling outage, s Class lE Qualified electronic analog equipment racks will be used to power the D? transmitters and process their outputs, with the reference leg and process temperature outputs, to compute the equivalent water \-
level. The racks will provide outputs to indicatoes in the control room, and to the computer.
RCP inlet temperature and motor current data will be processed by the computer to provide outputs for control room indication of coolant inventory trending when the RCPs are running.
A conceptual drawing of the system is shown in Figure 1. Individual parts of the system are described in the following paragraphs.
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4 . 1.' - ' TOP HOT LEG PRESSURE TAP n-The top hot leg pressure tap vill be located of f the hot leg -
high point vent. ,
, . .2. ' TOP REACTOR VESSEL PRESSURE TAP The top' reactor vessel..2pressure tap will be made - to a pene-
- tration intthe reactor vessel head _ presently occupied by a control 1 rod drive mechanism.
3 '.' SEAL CHAMBERS
' seal . chamber will be installed at the high point.of each -
reference leg to ensure that.the reference leg to each DP transmitter remains full of water. The seal chambers will-be water reservoirs only and will not contain a bellows or diaphragm. There will be three connections in the seal-i- chambers. One will be atethe top for connection to a vint-valve, one at the bottom for connection to the reference leg of the transmitter, and the third at the center line on
' one end for connection to the pressure tap.
4.. RMOVABLE. SECTION OF RV HEAD REFERENCE LEG A removable section of stainless' steel tubing will be in-
- stalled between the reactor vessel top tap and the refueling.
cavity , wall for _ removal during refueling. Tubing configura-tion will be .such as to allow for thermal expansion and move-ment of the reactor ' vessel head. ,
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l 5. - ' SUPPORT FOR RMOVABLE SECTION OF RV HEAD REFERENCE LEG
[- A' ram v'able support for the removable section of tubing' be-tween the RV head .and the refueling cavity wall will be.. in-stalled on the cavity wall to provide seismic support ' for the tubing.
6.- _ BOTTOM HOT LEG PRESSURE TAP w
The bottom hot leg pressure tap will be located of f the decay heat suction line, and is scheduled for installation du-ing l '
the 1983 refueling outage by FPC.
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- 7. DIFFERENTIAL PRESSURE TRANSMITTERS Differential pressure transmitters, qualified as Class 1E in s accordance'with IEEE 323-1974, will be used.
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Four transmitters will be installed, two narrow range and two wide range. Each will have provisions for zero suppression and elevation. Each pair of narrow- and wide-range transmit-ters will be powered independently from a separate Class 1E electrical power source. One pair will be completely redun-dant.
The DP transmitters will be mounted inside containment.
The narrow-range transmitters will be calibrated for approx-imately 12 f t of water which, when compensated for system temperature variations, will be equivalent to the level of the coolant in the reactor vessel, above the bottom of the hot leg, when the RCPs are tripped.
The vide-range transmitters will be calibrated for approxi-mately 50 f t of water which, When compensated for system temperature variations, will be equivalent to the level of coolant within the hot leg when the RCPs are tripped.
The DP measurement system will not be functional when the RCPs are running or during venting operations. It will, however, be designed to withstand the conditions that will exist at those times without damage, and be fully recoverable af ter-wards.
- 8. REFERENCE LEG TDiPERATURE MEASUREMENT The system design will include the use of strap-on RTDs on the vertical portions of the water-filled reference legs to provide the temperature input required to convert the DP measurement to the equivalent coolant level.
- 9. HOT LEG TEMPERATURE. MEASUREMENT RTDs already installed in the hot legs will provide the pro-cess water temperature input required by the DP measurement system.
- 10. ANALOG EQUIPMENT RACKS Class 1E Qualified electronic analog equipment racks will be used to power the dif ferential pressure transmitters and pro-cess the outputs to compute coolant level. The racks will contain interconnected plug-in modules which perform the func-tions of current to voltage conversion, summation, function generation, division, and isolation.
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Two independently powered racks will be used. Each rack will process one narrow-range and one wide-range channel. Outputs of the racks will be sent to analog indicators located in the control room and to the computer.
Input and output terminals on the modules will be availble for monitoring from the front of the racks. In addition, each of the input modules will have provision for insertion of a test jack, which will disconnect the normal transmitter input and connect a test input. This will be used for calibration and troubleshooting.
- 11. COOLANT INVENTORY TRENDING WITH RCPs RUNNING The system concept provides a design to track reactor coolant inventory with the RCPs running. - It uses measurements of RCP motor current to infer the density of the pumped fluid. It also uses pump inlet temperature in an algorithm with the pump current measurements to derive an estimate of the pumped fluid void fraction.
Existing (non-Class 1E) current transformers and RTDs (one each per pump) are used to provide pump current and pump inlet tem-perature signals for input to a computer. The computer will use those two inputs to:
- a. Calculate the corresponding saturated liquid and vapor densities for each temperature input.
- b. Combine the densities with the pump current inputs in accordance with the void fraction algorithm.
- c. Provide outputs for control room indication of the void fraction for any single pump, or the average i
void fraction for all pumps running, over a range of 15 to 40 percent void fraction.
Please refer to AttachmentII, entitled " Feasibility Study of Inventory Trending Methods with RC Pumps Operating."
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. 12. CONTROL ROOM INDICATION Analog coolant level indicators will be mounted on a panel in the control room in close proximity with the void fraction indica tors .
i During normal operation with the RCPs running, or during the venting operation, the data provided by the void fraction in-dicators will permit the operator to track the reactor coolant inventoty% The coolant level indicators will read of f scale high. Ov1.ational procedures will provide instructions to the operator that level indications are invalid under these condi-tions.
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W If the reactor coolant pumps are turned off and the system is not being vented, the coolant level indicators will pro-vide a true iudication of reactor coolant inventory in both the reactor and the hot legs.
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