ML20210E610

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Proposed Tech Specs Clarifying That Analysis Used to Allow Spent Fuel Storage in Spent Fuel Pool Region 2 Would Be Performed Using NTRC-approved Methodology
ML20210E610
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 02/05/1987
From:
DUKE POWER CO.
To:
Shared Package
ML20210E597 List:
References
TAC-60845, TAC-60846, NUDOCS 8702100329
Download: ML20210E610 (1)


Text

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BASES 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

The minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM The limitations on the Fuel Handling Ventilation Exhaust System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal absorbers prior to discharge to the atmosphere.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

ANSI N510-1975 will be used as a procedural guide for surveillance testing.

The methyl iodide penetration test criteria for the carbon samples have been made more restrictive than required for the assumed iodine removal in the s

accident analysis because the humidity to be seen by the charcoal adsorbers

  • may be greater than 70% under normal operating conditions.

t 3/4.9.12 FUEL STORAGE - SPENT FUEL STORAGE POOL The requirements for fuel storage in the spent fuel pool on 3.9.12 (a) and (b) ensure that:

(1) the spent fuel pool will remain subcritical during fuel storage; and (2) a uniform boron concentration is maintained in the water volume in the spent fuel pool for reactivity control.

The value of 0.95 or less for Keff which includes all uncertainties at the 95/95 probability /

confidence level as described in Section 9.1.2.3.1 of the FSAR is the acceptance criteria for fuel storage in the spent fuel pool.

Table 3.9-1 is conservatively developed in accordance with the acceptance criteria and methodology referenced in Section 5.6 of the Technical Specifications.

Storage in a checkerboaru configuration in Region 2 meets all the acceptance criteria referenced in Section 5.6 of the Technical Specifications and is verified in a semi-annual basis after initial verification through administrative controls.

i The Action Statement applicable to fuel storage in the spent fuel pool ensures that:

(1) the spent fuel pool is protected from distortion in the fuel storage pattern that could result in a critical array during the movement of fuel; and (2) the boron concentration is maintained at 2000 ppm during all actions involving movement of fuel in the spent fuel pool.

The Surveillance Requirements applicable to fuel storage in the spent fuel i

pool ensure that:

(1) fuel stored in Region 2 meets the enrichment and burnup limits of Table 3.9-1 or the K,77 1 0.95 acceptance criteria of art w lifying =:l"6; and (2) the baron concentration meets the 2000 ppm limit.

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