ML20207S782
| ML20207S782 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/13/1987 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20207S774 | List: |
| References | |
| ULNRC-1465, NUDOCS 8703200266 | |
| Download: ML20207S782 (3) | |
Text
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,un REVISloy 3
n-REFUELING OPERATIONS
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3/4.'J.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION i
3 9.4 The containment building penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four
- bolts, b.
A minimum of.one door in each airlock is closed, and c.
Each penetration providing' direct access from the containment atmosph2,re to the outside atmosphere shall be either:
1)
Closed by an isolation valve, blind flange, or manual valve, or
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2)
Be capable of being closed by an OPERABLE automatic containment purge isolation valve.
APPLICA8ILITY: During CORE ALTERATION 5 or movement of irradiated fuel within the containment.
ACTION:
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__ With the requirements of the above specification not satisfied, immediately
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suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. building.
r SURVE_lLLANCE REQUIREMENTS
- f. f.f. /
-+++ Each of the above required containment building penetrations shall be eletermineal tu be either in its closed / isolated condition or capable of being clnsed by an OPERABLE automatic containment-purge isolation valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> priur to the start of and at least once per 7 days during CORE
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Al.IERAI!ON,5 or movement of frradiated fuel in the containment building by:
a.
Verifying the penetrations are in their closed / isolated condition, or b.
Iesting the containment purge isolation valves per the applicable portions of Specification 4;6.3.2.
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CALIAWAY - UNil 1 3/4 9-4
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REVISION 1 3/4.9 REFUELING OPERATIONS (g..
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BASES 3/4.9.1 BORCN CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform baron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. The limitation on K of ff nogreaterthan0.95issufficienttopreventreactorcriticalitydurin$
refueling operations. The locking closed of the required valves during refueling operations precludes the possibility of uncontrolled boron dilution of the filled portions of the Reactor Coolant System. This action prevents flow to the RCS of unborated water by closing flow paths from sources of unborated water. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses.
3/4.9.2 INSTRUMENTATION The OPERA 8ILITY of the Source Range Neutron Flux Monitors ensures that redundant rionitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products.
This decay time is consistent with the assumptions used in the safety analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERASILITY and, closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
The OPERA 8ILITY of this system ensures the containment purge penetrations will be automatically isolated upon detection of high radiation levels within containment. The OPERABILITY of this system is required to restrict the release of radioactive materials from the containment atmosphere to the environment.
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rAl.TERY 8 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the i
facility status or core reactivity condition:s during CORE ALTERATIONS.
i CALLAWAY - UNIT 1 8 3/4 9-1
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ULNRC-1465 INSERT A 4.9.4.2 Verify the trip setpoint concentration value for Containment Purge Monitors (GT-RE-22, GT-RE-3 3) is set at less than or' equal to SE-3 uCi/cc during CORE ALTERATIONS or movement of irradiated
' fuel within the containment.
. INSERT B The restriction on the setpoint for GT-RE-22 and GT-RE-33 is based on a fuel handling accident inside the Containment Building with resulting damage to one fuel rod and subsequent release of 0.1% of:the noble gas gap activity, except for 0.3% of the Kr-85 gap activity.
The setpoint concentration of SE-3 uCi/cc is equivalent to_approximately 150 mR/hr submersion dose rate.
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