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NESC1090 RCSLK9.

RCSLK9, PWR Coolant System Leak Rate

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1. NAME OR DESIGNATION OF PROGRAM:  RCSLK9.
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2. COMPUTERS
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Program name Package id Status Status date
RCSLK9 NESC1090/01 Tested 26-OCT-1988

Machines used:

Package ID Orig. computer Test computer
NESC1090/01 IBM PC IBM PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

RCSLK9 was developed to analyze the leak tightness of the primary coolant system for any pressurized water reactor (PWR). From given system conditions, water levels in tanks, and certain system design parameters, RCSLK9 calculates the loss of water from the reactor coolant system (RCS) and the increase of water in the leakage collection system during an arbitrary time interval. The program determines the system leak rates and displays  or prints a report of the results. During the initial application to a specific reactor, RCSLK9 creates a file of system parameters and saves it for future use.
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4. METHOD OF SOLUTION

RCSLK9 provides the inspector with the capability to independently analyze the leak tightness of PWR reactor coolant systems. By taking two sets of water inventory data  in the RCS and in leak collection tanks, separated by a time interval, and applying RCSLK9, the inspector can obtain the gross leak rate for the RCS and the rate at which the leakage is being collected. The gross leak rate for the cooling system is found by dividing the inventory loss in pounds by the product of the elapsed  time between inventories and the density of water. The quotient is converted to gallons per minute. To determine the identified leak rate for the RCS and the chemical and volume control system (CVCS) during the test, the amount of water collected in the pressurizer relief tank and the reactor drain tank must be calculated. Water inventories for the pressurizer relief tank and the reactor drain tank are determined from measured levels and the tank calibration curves or tank dimensions. To find the identified leak rate for the  cooling system, RCSLK9 divides the combined inventory gain in pounds for the reactor drain tank and the pressurizer relief tank by the product of the elapsed time between inventories and the density of water. The test data required for calculating the identified leak rate are the water levels in the tanks and the test duration. The unidentified leak rate is calculated by subtracting the identified leak rate from the gross leak rate.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

RCSLK9 assumes that  the hot and cold legs of the RCS have equal volumes.
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6. TYPICAL RUNNING TIME

Only a few seconds are required to perform the leak calculations on an IBM PC/AT.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

RCSLK9 was adapted from RCSLK8, which was written in CBASIC for the Osborne 1 computer.
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9. STATUS
Package ID Status date Status
NESC1090/01 26-OCT-1988 Tested at NEADB
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10. REFERENCES:
NESC1090/01, included references:
- D.C. Kirkpatrick, R.W. Woodruff, and R.A. Holland :
  RCSLK9: Reactor Coolant System Leak Rate Determination for PWRs
  User's Guide
  NUREG-1107 (December 1984)
- D.C. Kirkpatrick, R.W. Woodruff, and P. Bell :
  RCSLK9: Reactor Coolant System Leak Rate Determination for PWRs
  User's Guide: Installation Procedures
  NUREG-1107 ADDENDUM (December 1986)
- L. Eyberger :
  RCSLK9 Flexible Disk Cartridge Description
  and Implementation Information
  NESC Note 87-66 (May 14, 1987)
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11. MACHINE REQUIREMENTS

IBM PC, or compatible, with one double-sided  disk drive and 64K bytes or greater RAM.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC1090/01 BASIC
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  DOS 2.0, 2.10.
NESC1090/01
The test case was run on a IBM PC/AT under MS/DOS 3.21  with BASIC version D3.21.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The nomenclature in the reference report is appropriate for Westinghouse PWRs.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          D.C. Kirkpatrick
          Office of Nuclear Reactor Regulation
          U.S. Nuclear Regulatory Commission
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16. MATERIAL AVAILABLE
NESC1090/01
File name File description Records
NESC1090_01.001 INFORMATION FILE 94
NESC1090_01.002 RCSLK9 BASIC SOURCE 1133
NESC1090_01.003 CALC BASIC SOURCE 557
NESC1090_01.004 LIST OF DOCKET NUMBERS 18
NESC1090_01.005 POLISADES 1 PARAMETER LIST 45
NESC1090_01.006 POINT BEACH 1 PARAMETER LIST 45
NESC1090_01.007 PRAIRIE ISLAND 1 PARAMETER LIST 45
NESC1090_01.008 ZION 1 PARAMETER LIST 45
NESC1090_01.009 POINT BEACH 2 PARAMETER LIST 45
NESC1090_01.010 ZION 2 PARAMETER LIST 45
NESC1090_01.011 KEWAUNEE 1 PARAMETER LIST 45
NESC1090_01.012 PRAIRIE ISLAND 2 PARAMETER LIST 45
NESC1090_01.013 RANCHO SECO 1 PARAMETER LIST 45
NESC1090_01.014 D. C. COOK 1 PARAMETER LIST 45
NESC1090_01.015 D. C. COOK 2 PARAMETER LIST 45
NESC1090_01.016 CALVERT CLIFFS 1 PARAMETER LIST 45
NESC1090_01.017 CALVERT CLIFFS 2 PARAMETER LIST 45
NESC1090_01.018 THREE MILE ISLAND 2 PARAMETER LIST 45
NESC1090_01.019 TROJAN 1 PARAMETER LIST 45
NESC1090_01.020 DAVIS BESSE 1 PARAMETER LIST 45
NESC1090_01.021 FARLEY 1 PARAMETER LIST 45
NESC1090_01.022 LOGO BASIC SOURCE 46
NESC1090_01.023 BATCH FILE TO EXECUTE LOGO 1
NESC1090_01.024 BATCH FILE TO EXECUTE LOGO 1
NESC1090_01.025 BATCH FILE TO EXECUTE RCSLK9 1
NESC1090_01.026 BATCH FILE TO SET UP A BOOTABLE DISK 3
NESC1090_01.027 DOS file names 26
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: inspection, leakage, pwr reactors, reactor cooling systems.