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23 of 24 FIGURE A2 INJECTION REQUIRED TO REPLACE WATER LOST BY BOILING DUE TO DECAY HEAT FOR A 3000MW(th) PLANT Discussion These curves show the amount of water that must be injected into the vessel to replace water lost due to decay heat. This curve is based on a 3000 MW(th) plant operated at a constant power for an infinite period and then shut down instantaneously. This is the minimum amount of water that must be injected into a core to cool it once it is shutdown (Source: NRC93). Step 1 Determine the amount of water injection required by: w = wf°°° where: W, = W,3000 = p = pim, 3000 [MW(th)} Water injection required [m3/h] Water injection required for 3000 MW(th) plant [m3/h] from figure below size of the plant in MW(th) [MW(th) • 3 x MW(e)] Step 2 If the core has been uncovered for greater than 15 minutes increase the injection rate by a factor of three to accommodate the heat from the Zr-H2O reaction and built up energy.

62 Performed by: PROCEDURE A3 Nudear Condition Assessment Manager ASSESSMENT OF RELEASE ROUTES AND CONDITIONS Pg. Iof4 Purpose: To estimate potential and actual atmospheric release routes and conditions. Discussion The release route conditions are crucial to interpreting environmental measurements. All potential release routes should be examined to ensure that releases are not missed and operations do not result in undetected or unmonitored releases. Input Plant system conditions Output >• Estimated potential and actual release routes and conditions.

H, concentration > (insert site specific value). Intentional venting of containment 100% per day Containment has a design leak rates > 1 % per day and is isolated Containment is not fully isolated. 1% per day Containment has a design leak rates < 1 % per day and is isolated Containment by-pass under dry conditions 100% per hour Primary system is at high pressure. 100% per day Primary system is depressurized. Containment by-pass under wet conditions 100 mVh Multiple steam generator tube ruptures (SGTR) 100% of the coolant in 1 h.

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Generic assessment procedures for determining protective actions during a reactor accident by International Atomic Energy Agency


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