ML20133M296

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Proposed Tech Specs Imposing New Surveillance Requirements for Reactor Scram Breakers Necessitated by Installation of Automatic Shunt Trip Circuits for Breakers
ML20133M296
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 08/08/1985
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20133M286 List:
References
TAC-53186, TAC-53187, NUDOCS 8508130080
Download: ML20133M296 (3)


Text

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TABLE 15.4.1-2 (Continued)

Test Frequency

24. - Integrity of Post Accident Evaluate Yearly Recovery Systems Outside
  • Containment
25. Containment Purge Supply Verify valves are Monthly (9) l and Exhaust Isolation Valves locked closed
26. Reactor Trip Breakers a. Verify independent Monthly (9) operability of automatic shunt and undervoltage trip functions.
b. Verify independent Each refueling l-operability of man- shutdown ual trip to shunt and undervoltage trip functions.
27. Reactor Trip Bypass Breakers a. Verify operability Prior to of the undervoltage breaker use trip function.
b. Verify operability Each refueling of the shunt trip shutdown functions.
c. Verify operability Each refueling of the manual trip shutdown to undervoltage trip functions.

(1) R_equired only during periods of power operation.

(2) E determination will be started when the gross activity analysis of a filtered sample indicates >10pCi/cc and will be redetermined if the I primary coolant gross radioactivity of a filtered sample increases by g more than >10pci/cc.

(3) Drop test shall be conducted at rated reactor coolant flow. Rods shall be dropped under both cold and hot condition, but cold drop tests need not

'be timed.

(4) Drop tests will be conducted in the hot condition for rods on which maintenance was performed.

(5) As accessible without disassembly of rotor.

(6) Not required during periods of refueling shutdown.

(7) At least once per week during periods of refueling shutdown.

(8) At least three times per week (with maximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples) during periods of refueling shutdown.

(9) Not required during periods of cold or refueling shutdown.

(10) During end-of-cycle period of operation when boron concentration is less than 100 ppe, this test may be waived due to operational limitations.

(11) Sample to be taken after a minimum of 2 EFPD and 20 days power operation since the reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

8500130080 850000 PDR ADOCK 0500026 P PDR-

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15.6.8 PLANT OPERATING PROCEDURES (Continued) 15.6.8.4 The following programs shall be established, implemented, and maintained.

A. Post-Accident Sampling

  • A program **which will ensure the capability to obtain and analyze reactor coolant, containment atmosphere, and in-plant gaseous effluent samples under accident conditions. The program shall include the following:

(i) Training of personnel; (ii) Procedures of sampling and analysis; and (iii) Provisions for maintenance of sampling and and analysis equipment.

  • Post-Accident Coolant Sampling and Post-Accident Containment Atmospheric Sampling Systems.

l

    • It is acceptable if the licensee maintains details of the program in i plant operation manuals.

l

~Enit1AmendmentNo.92 15.6.8-3 August 7, 1985 Unit 2 Amendment No. 96

. l G. Failure of Containment High-Range Radiation Monitor A minimum of two in-containment radiation-level monitors with l 8 7 a maximum range of 10 rad /hr (10 /hr for photons only) should l

be operable at all times except for cold shutdown and refueling outages. This is specified in Table 15.3.5-5, item 7. If the minimum number of operable channels are not restored to operable condition within seven days after failure, a special report shall be submitted to the NRC within thirty days following the event outlining the action taken, the cause of the inoperability 1 and the plans and schedule for restoring the system to operable status.

H. Failure of Main Steam Line Radiation Monitors If a main steam line radiation monitor (SA-11) fails and cannot be restored to operability in seven days, prepare a special l report outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the channel to operable tatus within thirty days of the event.

i Unit 1 - Amendment No. 92 15.6.9-11 August 7, 1985 Unit 2 - Amendment No. 96 L