ML20203N981

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Proposed Tech Specs,Adding New Section 3.24, RCS Leakage Detection Sys
ML20203N981
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 04/25/1986
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20203N963 List:
References
NUDOCS 8605060250
Download: ML20203N981 (3)


Text

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3.24 Reactor Coolant System Leakage Detection Systems Applicability: Modes I,2,3 and 4 Objec tive: To specify imary plant operability based upon the Reactor Coolant System Leakage Detection Systems Specification:

A.(1) The Containment Atmosphere Gaseous Radioactivity Monitoring System shall be operable whenever in the applicable modes of Plant operation.

(2) The Volume Control Tank Level Monitoring System and either the Containment Instrument Sump or the Containment Main Sump Level Monitoring System shall be operable whenever in the applicable modes of Plant operation.

B.(1) With the Containment Atmosphere Gaseous Radioactivity Monitoring System inoperable, operation may continue provided grab samples of the containment atmosphere are obtained and analyzed for gross noble gas activity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Restore the inoperable monitor to OPER ABLE status within 7 days or, in lieu of any report required by Specification 6.9.2, prepare and submit a special report to the Commission pursuant to Specification 6.9.3 within 30 days outlining actions taken, cause of inoperability and plans for restoring the monitor to OPERABLE status.

(2) With the Volume Control Tank Level Monitoring System or both the Containment Instrument Sump and the Containment Main Sume Level Monitoring System Inoperabic be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Basis:

The RCS Leakage Detection Systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary.

This technical specification ensures a reliable means of detecting unidentified leakage in the reactor coolant system which potentially could be due to a circumferential through-wall flaw in primary system piping. The required instrument sensitivity is I gallon per minute in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as stated in Condition (2) of Generic Letter 84-04. Because the Volume Control Tank Level Monitoring System and the Containment Sump (Main and Instrument) Level Monitoring Systems are not seismically qualified, surveillance requirements for a seismic event greater than one half the Safe Shutdown Earthquake (SSE) are imposed.

Surveillance requirements for the Reactor Coolant System Leakage Detection Systems are included in Table 4.2-1.

3-47 8605060250 860425 PDR ADOCK 05000213 p PDR

Table 4.2-1 (continued)

Channels Action Minimum Frequency S. Variable Low Pressure Calibrate Each refueling trip set point calculator Check Each shif t

9. Rod Position Calibrate Each refueling Digital Voltmeter Check with Every six inches of counters rod motion when data logger is out of service.

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10. Rod Position Counters Test Each refueing Check with Every six inches of rod Digital motion when data Voltmeter logger is out of service.
11. Steam generator level Calibrate Each refueling Check Each shif t
12. Steam generator flow Calibrate Each refueling mismatch Check Each shi!t
13. Charging Flow Calibrate Each refueling
14. Residual Heat Pump Flow Calibrate Each refueling
15. Boric Acid Tank Level Calibrate Each refueling Check Each week
16. Refueling Water Storage Calibrate Each refueling Tank Level Test 90 days
17. Volume Control Tank Level Calibrate Each refueling' Test 90 days l

Check Each day

18. Reactor Containment Calibrate Each refueling Pressure Check Each day
19. Radiation Monitoring System Calibrate Each refueling Test Each day
20. Boric Acid Control Calibrate Each refueling
21. Containment Sump Level Calibrate Each refueling Check Each day' l
22. Valve Temperature Test Each refueling Interlocks
23. Pump Valve Interlock Check Each refueling 4-2b

e Table f5.2-1 (continued)

Channels Action Minimum Frequency

24. Reactor Coolant System OPS Calibrate Each refueling Test Each refueling
25. Auxiliary Feedwater Flow Calibrate Each refueling Rate Check Each Month
26. Reactor Coolant System Calibrate Each refueling Subcooling Margin Monitor Check Each Month
27. PORV Position Indication Calibrate Each refueling (Acoustic Monitor) Check Each Month
23. PORY Block Valve Calibrate Each ref ueling Position Indication
29. Safety Valve Position Calibrate Each refueling Indication (Acoustic Check Each Month Monitor)
30. Containment Instrument Calibrate Each refueling Sump Level Check Each day
  • Note:

Following any seismic event greater than one half the Safe Shutdown Earthquake (SSE) the indicated calibration, or check sha!! be performed prior to declaring such affected instruments operable.

4-2c

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