ML20138R610

Proposed Tech Spec Note 1 for Table 3.1.1 & Note 1 for Table 3.2.A,adding Formal Time Limit for Keeping Reactor Protection Sys & Primary Containment Isolation Sys Equipment Out of Svc During Testing & Calibr

ML20138R610
Person / Time
Site:	Pilgrim
Issue date:	12/23/1985
From:	BOSTON EDISON CO.
To:
Shared Package
ML20138R554	List: BECO-85-227, Application for Amend to License DPR-35,consisting of Proposed Change 85-15,revising Note 1 to Table 3.1.1 & Note 1 to Table 3.2.A,adding Formal Time Limit for Keeping Equipment Out of Svc During Testing & Calibr.Fee Paid ML20138R610
References
NUDOCS 8512310395
Download: ML20138R610 (2)

Text

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"* NOTES FOR TABLE 3.1.1

1. There shall be two operable or tripped trip systems for each function. An instrument channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter. If the minimum number of operable instrument channels per trip system cannot be met for both' trip systems, the appropriate actions listed below shall be taken.

I A. Initiate insertion of operable rods and complete insertion of al' operable rods within four hours.

B. Reduce power level to IRM range and place mode switch in the startup/

hot standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C. Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

D. Reduce power to less than 45% of design.

2. Permissible to bypass, with control rod block, for reactor protection system reset in refuel and shutdown positions of the reactor mode switch.

3. Permissible to bypass when reactor pressure is (600 psig.

4 Permissible to bypass when turbine first stage pressure is less than 305 psig.

5. IRM's are bypassed when APRM's are onscale and the reactor mode switch is in the run position.

6. The design permits closure of any two lines without a scram being initiated.

7. When the reactor is subcritical, fuel is in the reactor vessel and the reactor water temperature is less than 212*F, only the following trip functions need to be operable:

A.~ Mode switch in shutdown

8. Manual scram C. High flux IRM

, D. Scram discharge volume high level E. APRM (15%) high flux scram

8. Not required to be operable when primary containment integrity is not required.

9. Not required while performing low power physics tests at atmospheric pressure during or af ter refueling at power levels not to exceed 5 MW (t).

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• NOTES FOR TABLE 3.2.A

1. Whenever' Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function. An instrument channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same ti o system is monitoring that parameter; or, where only one channel exists per trip system, the other trip system shall be operable.

2. Action If the first column cannot be met for one of the trip systems, that trip system shall be tripped. If the first column cannot be met for both trip systems, the appropriate action listed below shall be taken.

A. Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24, hours.

B. Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.

C. Isolate Reactor Water Cleanup System.

D. Isolate Shutdown Cooling.

3. Instrument set point corresponds to 129.5" above top of active fuel.

4. Instrument set point corresponds to 78.5" above top of activ9 fuel.

5. Not required in Run Mode (bypassed by Mode Switch).

6. Two required for each steam line.

7. These signals also start SBGTS and initiate secondary containment isolation.

8. Only required in Run Mode (interlocked with Mode Switch).

9. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to'the planned start of hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of hydrogen injection and prior to establishing reactor power-levels below 20% rated power.

Amendment No. 46