3F1290-01, Forwards Improved Design Control Documentation for Crystal River Unit 3 Design Basis for Post-Accident Monitoring Instrumentation
| ML20065N456 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/05/1990 |
| From: | Beard P FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20065N460 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 3F1290-01, 3F1290-1, NUDOCS 9012120141 | |
| Download: ML20065N456 (3) | |
Text
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i Power Cr stel iver$tt3 Docket No. 50-302 December 5, 1990 3F1290 01 Attention: Document Control Desk U.S. Nuclear Regulatory Commission y Washington, D.C. 20555
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Subject:
Regulatory Guide 1.97 Post Accident Monitoring
Reference:
FPC to NRC letter dated August 2, 1990 ;
Dear Sir:
The purpose of this letter is to transmit a complete set of updated Regulatory Guide 1.97 Variable Data Sheets which reflect modifications and changes through Refuel 7. The attached Variable Data Sheets were prepared and updated in accordance with'. the information requirements specified in RG 1.97. A cross :
referenced index is provided to compare the individual variables from )ast transmittals to the Design Basis Document sheets attached to this letter. T1cse
- sheets have been-integrated into the FPC Design Basis Document System and future i updates will be controlled by FPC existing engineering procedures. This letter completes the florida Power Corporation (FPC) action stated in the above reference.
Sincerely,
.-I;eard, Jr.
Senior.Vice President Nuclear Operations
.PMB:EMG xc: Regional Ad'mii11strator, Region 11 Senior. Resident inspector
-NRR Project Manager
'9012120141 901205 hlH ADOCK 05000302 L
PDC POST OFFICE BOX 219
- CRYSTAL RIVER, FLORioA 32629 0219 * (904) 79$4486 A Florida Progress Company h0h
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I M LE OF CONTENTS 3/21/88 NRC DBD Page No, SUBMITTAL. X-Ref.
VARIABLE 01 5 Neutron Flux 02 6 Control Rod Position- 03 7
- RCS Soluble Boron Content 04 8 RCS Hot leg Water Temperature 9 05 RCS Cold Leg Water Temperature 06 11 RCS Pressure 07 12 Reactor Vessel Level 08 13 Degrees of Subcooling 09 14 Containment Sump Water Level (Harrow Rnge) 4 10 15 Containment Water Level (Flood Range)
Containment isolation Valve Position (Manual Valves) llA 16 118 17 Containment Isolation Valve Position (Automatic Valves) 12 18-20 Core Exit Temperature 22 13 RCS Radioactivity Concentration 14 23 )
Containment Hydrogen Concentration 24 )
15 Containment Pressure 16 25 l RHR System Flow (Decay Heat) 26 RHR Heat Exchanger Outlet Ttg erature (Decay Heat) 17 i
18A 27 Accumulator Tank Level (Core (lwd Tank) 188 28 A:cumulator TankValve Accumulator Isolation Pressure Position (Core (Core FFlood Tank) lood. Tank) 19
'20 29 30 J Boric Acid Charging Flow 31&32 21 Flow in HPl System 25 22 l Flow in LPI System 33 23 Refueling Water Storage Tank Level (Borated Water Storage Tank) 35 24 Reactor Coclant Pump Status 36 Primary System Safety Relief Valve Position or ilow Through 25 or Pressure in Reli 1 Liner 26 37 Pressurizer Level 27 3r Pressurizer Heater Status 28 40
- Quench Tank Level (Reactor Coolant Drain rank) 29 41 Quench-Tank Temperature (Reactor Coolant Drain Tank) 42 30 Quench Tank Pressure (Reactor Coolant Orain Tank) . 31 43 Steam Generator Level 32 44 Steam Generator. Pressure 33 45
'Hs'.n Steam Safety Relief Valve Position 46 34-Main Feedwater Flow 35 47 Auxiliary Feedwater Flow 48 Condensate Storage Tank Water Level (Emergency Feedwater Tank) 35 37 49 Containment Spray. Flow 50 Heat Removal by the Containment Fan Heat Removal System 38 39 52
. Containment Atmosphere Temperature 53 Containment Sump Water Temperature 40 41 55 Make up Flow - In 42 56 Letdown Flow - Out- 43 57 Volume Control Tank level (Makeup Tank) 59 44 Component Cooling Water Temperature .to ESF Systems a m_
IABLEOFCONTENTS(Cont'd) 3/21/88t<RC OBD Page No.
SUBMITTAL. X Ref.
VARIABLE 45 60 Component Cooling Water Flow to ESF Systems (Level) 46 61 High Level Radioactive 1.iquid Tank level 47 62 Radioactue Gas Hold up Tank Pressure (Waste Decay Tanks) 48 63 Emergency Ventilation Damper Position
'E Status of Standby Power High Range 49 50 64 65 Containment Area Radiation 51 66 Radiation Exposure Rate Inside Buildings or Areas Where Access is Required to Service Equipment Important to Safety or which are in Direct Contact with Primary Containment where Penetrations and Hatches are Locates 52 68 Containment or Purge Effluent, Noble Gas 53 69 Reactor Shield Building Annulus 54 70 Auxiliary Building, Noble Gas 55 71 Condenser Air Removal System Exhaust 56 70 Common Plant Vent 57 72 Vent from Safety Valves or Atmospheric Dump Valves 58 68&70 All Other Identified Release Points 59 73 All Identified Plant Release Points Particulates and Halogens 60 74 Airborne Radio Halogens and Particulates 61 75 Plant and Environs Radiation, Portable Instrumentation 62 76 Plant and Environs Radioactivity 63 77 Wind Direction 64 78 Wind Speed 65 79 Estimation of Atmospheric Stability 66 80 Primary Coolant and Sump (Grab Sample) - Gross Activity 67 81 Gamma Spectrum Primary Coolant and Sump (Grab Sample) 68 82 Primary Coolant and Sump (Grab Sample) - Boron Content 69 83 Primary Coolant and Sump (Grab Sample) - Chloride Content 70 84 Primary Coolant and Sump (Grab Sample) - Dissolved Hydrogen Total Gas 71 85 Primary Coolant and Sump (Grab Sample) - Dissolved Oxygen 72 86 Primary Coolant and Sump (Grab Sample) - pH 73 87 Primary Coolant and Sump (Grab Sample) - Hydrogen Content 74 88 Containment Air (Grab Sample) - Oxygen Content 90 75 Primary Coolant and Sump (Grab Sample) - Gamma Spectrum
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