B13577, Proposed Tech Specs Re Refueling Operations
| ML20058M851 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/07/1990 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20058M849 | List: |
| References | |
| B13577, NUDOCS 9008130090 | |
| Download: ML20058M851 (3) | |
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-Docket No. 50-336 B13577 a
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.p es Millstone Nuclear Power Station, Unit No. 2 Proposed Changes-to Technical Specifications Refueling Operations
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REFUELING OPERATIONS j
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SPENT FUEL POOL TEMPERATURE LIMITING CONDITION FOR OPERATION
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3.9.3.21 The spent fuel pool; bulk temperature shall be maintained at less than or. equal ' to 140'F. -
y; APPLICABILITY: Whenever irradiated fuel is stored in the spent fuel pool.
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/ ACTION::
u With the above conditions not. satisfied;;
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- Immediate initiate actions to restore the' spent fuel-pool tempera-ture toLless than or equal, to 140'F, and i
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Within one hour,' suspend all fuel movement in the spent fuel pool, and
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- c.. Within one hour, isolate the spent fuel pool cleanup domineralizers, and 1
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At-least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, record the spent fuel pool bulk tempera-ture.'
s SURVEILLANCE-REQUIREMENTS i
4~.9.3.2 - The spent fuel pool. bulk temperature shall be. verified to be less than or equal: to-140*F at-least once.per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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L' MILLSTONE - UNIT 2 3/4 9-3a Amendment No. JJf l
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~X b'/4.9 REFUELING OPERATIONS
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BASES
!3/4.9.1 BORON CONCENTRATION
.. The'11mitations on reactivity conditions during REFUELING ensure that:
'1) the reactor will remain. suberitical during - CORE ALTERATIONS, and 2) a uniform boron ~ concentration is maintained for reactivity control in the water volume-having direct access to the reactor vessel. -These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
3/4.9.2 -INSTRUMENTATION LThe OPERABILITY of the source range neutron flux monitors ensures that redundant ~ monitoring capability is available to detect changes in the reactiv-
~ity condition of the core.
3/4.9.3 DECAY TIME
. The; minimum' requirement for reactor suberiticality prior to movement of
' irradiated fuel ensures that sufficient time has elapsed to allow the rEioac-tive decay of the short-lived fission products. This decay time is con.. stent with. the assumptions used in the accident analyses.
' The requirement that the spent fuel pool bulk temperature be maintained below 140*F ensures that high water temperature will not degrade resin in the o
spent. fuel pool-demineralizers and that the temperature and humidity above the-pool are compatible with personnel comfort and safety requirements. Addition-ally, the' requirement ensures that -the design temperature of the fuel pool
- cooling ' system,l liner / building structures, and. racks are not exceeded.
The requirement for the reactor to remain in-MODE 5 or 6 until the most recent 1/3 core offload has decayed 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> ensures that ' alternate cooling is available during this time to cool the spent fuel pool should a failure occur in the spent fuel pool cooling system.
The shutdown cooling (SDC) system is a high capacity system; that is, one train is sufficient to cool both the core and the spent fuel pool should a failure ' occur'in the spent fuel
-pool cooling system within 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> from reactor shutdown.
-3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based epon the lack of containment pressurization poten-1
- tial while in the REFUELING MODE.
3/4.4.5 COMMUNICATI0Ei The requirement for communications capability ensures that refueling station personne1' can be promptly informed of significant changes in the facility status or core reactivity condition during fuel or CEA movement within the reactor pressure vessel.
MILLSTONE - UNIT 2 B 3/4 9-1 Amendment No. 72, W
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