ML17347A299

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Proposed Tech Specs Incorporating plant-specific Specs for Reactor Vessel Level Monitoring Sys
ML17347A299
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 02/20/1987
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17347A298 List:
References
NUDOCS 8703020462
Download: ML17347A299 (8)


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TABLE 3.5-5 (Continued)

ACTION STATEMENTS ACTION 1 With the number of OPERABLE accident monitoring instrumentation channel(s) less than the Total Number of Channels shown in Table 3.5-5. either restore the inoperable channel(s) to OPERABLE status within 7 days, or be in a condition with Keff, 0.99, 96 thermal power excluding decay heat equal to zero, and an average coolant temperature Tavg, 350oF within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 2 With the number of OPERABLE accident monitoring instrumentation channels less than the minimum channels OPERABLE requirements of Table 3.5-5, either restore the inoperable channel(s) to OPERABLE status within 08 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in a condition with Keff p 0.99, % thermal power excluding decay heat equal to zero, and an average coolant temperature Tavg, 350oF within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 3 Operation may continue up to 30 days with less than minimum channels OPERABLE for narrow range instruments.

ACTION 0 Or close the associated block valve and open its circuit breaker.

ACTION 5 With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

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1) either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or
2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 within 30 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

ACTION 6 , With one hydrogen monitor inoperable, restore the inoperable monitor to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 7 With both hydrogen monitors inoperable, restore at least one monitor to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION S With the number of OPERABLE Channels one less than the Total Number of Channels restore the system to OPERABLE sfatus within 7 days. If repairs are not feasible without shutting down, prepare and submit a Special Report to the commission pursuant to the specification 6.9.3(k) within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

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Amendment Nos.

~ i ~ r TABLE 3.5-5 (Continued)

ACTION STATEMENTS ACTION 9 V/ith the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements, restore the inoperable channel(s) to OPERABLE status within 08 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. If repairs are not feasible without shutting down:

l. Initiate an alternate method of monitoring the reactor vessel inventory; and
2. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3(k) within 30 days following. the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and
3. Restore both channels to OPERABLE status at the next scheduled refueling. (See Note 1 below)

Amendment Nos. and NOTE:

1) Refer to Bases Page B3.5-1 for additional guidance.

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With untreated gaseous effluents exceeding the limits of 3.9.2.e pursuant to Specification 3.9.2.e.3, submit a report which includes the following information:

(1) Identification of the inoperable equipment or subsystems and the reason for inoperability, (2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and (3) Summary description of action(s) taken to prevent a recurrence.

With the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC from all uranium fuel cycle sources exceeding the limits of Technical Specification 3.9.2.h, submit a report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.9.2.h and includes the schedule for achieving conformance with those limits. This report, as defined in 10 CFR Part 20.005c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceeds the limits of Specification 3.9.2.h and if the release condition resulting in violation of 00 CFR Part 190 has not already been corrected, the report shall include a request for a variance in accordance with the provisions of 00 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

With the measured levels of radioactivity in environmental samples as a result of plant effluents pursuant to Specification 0.12.l.b, submit a report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential dose to a MEMBER OF THE PUBLIC is less than the limits of Specifications 3.9.1.b, 3.9.2.b and 3.9.2.c.

If the limits of Technical Specification 3.20 are exceeded, submit a report describing the cause of the unavailability, action taken and a schedule for restoration within 30 days.

Reactor Vessel Level Monitoring System, Reference Table 3.5-5, Action Statements 8 and 9.

6-23 Amendment Nos. and

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B3.5 BASES FOR LIMITINGCONDITIONS FOR OPERATION INSTRUMENTATION This specification outlines limiting conditions for operation necessary to preserve the effectiveness of the reactor and safety features instrumentation systems when any one or more of the channels is out of service.

Almost all reactor protection channels are supplied with sufficient redundancy to provide the capability for channel calibration and test at power. Exceptions are backup channels such as reactor coolant pump breakers. The removal of one trip channel is accomplished by placing that channel bistable in a tripped mode; e.g., a two-out-of-three circuit becomes a one-out-of-two circuit. Testing does not trip the system unless a trip condition exists in a concurrent channel.

Reactor Vessel Level Monitorin S stem In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only be possible during the next refueling outage. This is because the sensors are accessible only after the missile shield and reactor vessel head are removed. It is not feasible to repair a channel except during a refueling outage when the missile shield and reactor vessel head are removed to refuel the core. If only one channel is inoperable, it shall be restored to OPERABLE status in a refueling outage as soon as reasonably possible. If both channels are inoperable, both channels should be restored to OPERABLE status in the nearest refueling outage.

If circumstances do not allow restoration of both channels to an operable status during a REFUELING outage, an emergency Technical Specification amendment or discretionary enforcement, could be requested to allow for restart of a unit with one channel inoperable. The request would have to provide sufficient justification as to why a unit restart from a REFUELING outage would be acceptable with one channel inoperable.

Reference:

FSAR - Section 7.2.1 B3.5-1 Amendment Nos. and

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