ML20077E015
| ML20077E015 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/30/1991 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20077D966 | List: |
| References | |
| NUDOCS 9106050386 | |
| Download: ML20077E015 (4) | |
Text
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'*'g..
TABLE 15.4.1-1 (3 ef 4).
No. Channel Description Check Calibration Igjit Remarks 24.. Containment Pressure S
R M**
Narrow range containeent pressure
(-3.0, +3 psig excluded) vu,o Sg 25.' Steam Generator Pressure S***
R M**
w r>3
- 26. Turbine First Stage Pressure S**
R M**
i co l
ow Om
- 27. Emergency Plan Radiation Survey Q
R Q
Instruments 02 gg
- 28. Environmental Monitors M
N.A.
N.A.
moo CW f jde~d 'only~%en~the_is in
~~
Eij*
- 29. Overpressure Mitigating S
R oveyressurel mitigation..systes,
.operatiog
- 30. PORY Position Indicator S
R R
- 31. PORV Block Valve Position Q
R N.A.
Indicator
- 32. Safety Valve Position M
R N.A.
Ind'.cator
- 33. PORV Operability N.A.
R M
Performance of a channel functional test but excluding valve operation
- 34. Subcooling Margin Monitor M
R N.A.
- 35. Undervoltage on 4 KV Bus N.A.
R M**
For Auxiliary Feedwater Pump Initiation
- 36. Auxiliary Feedwater Flow Rate See R
N.A.
Flow Rate indication will be checked at Remarks each unit startup and shutdown
- 37. Degraded 4.16 KV Voltage S
R M**
- 38. a.
Loss of Voltage (4.16 KV)
S R
M**
b.
Loss of Voltage (480 V)
S R
M**
- 39. 4160 V Frequency N.A.
R N.A.
Unit 1 - Amendment No. 113 April 14, 1988 Unit 2 - Amendment No. 116 j
1 i
TABLE 15.4.1-2 (Continued) 1911 LttQEMI 8.
Secondary Coolant Gross Beta-gamma Weekly "
t Activity or gamma isotopic analysis lodine concentration Weekly when gross Beta-gamma activity equals or exceeds 1.2 pCi/cc '"
9.
Control Rods Rod drop times of all Each refueling or full length rods "'
after maintenance that couldaffectp' roper f
i functioning
]
1
- 10. Control Rod Partial movement of Every 2 weeks '"
all rods
- 11. Pressurizer Safety Valves Set point Every five years ""
- 12. Main steam Safety Valves Set Point Every five years ""
- 13. Containment Isolation Trip functioning Each refueling shutdown
- 14. Refueling System Interlocks functioning Each refueling shutdown
- 15. Service Water System functioning Each refueling shutdown
- 16. Primary System Leakage Evaluate Monthly '"
- 17. Diesel fuel Supply fuel inventory-Daily
- 18. Turbine Stop and Governor functioning Monthly '"""
Valves
- 19. Low Pressure Turbine Visual and magnetic Every five years Rotor inspection '"
particle or liquid 1
penetrant
- 20. Boric Acid System Storage Tank Daily Temperature
- 21. Boric Acid System Visual observation Daily of piping ' temperatures (all_ > 145 f)
- 22. Boric Acid Piping ileat Electrical circuit Monthly Tracing operability
- 23. PORV Block Valves
- a. Complete Valve Cycle Quarterly
(" ""
b'L0 pen position check Every72hoursJ(14)'
l Unit.1 - Amendment No. 106 Page 2 of 4 March 23, 1987 l
Unit 2 - Amendment No. 109
1ABLE 15.1ADLE 15.4.1-2 (Continued) hu Lttucau Integrity of Post Accident Evaluate Each refueling Recovery Systems Outside cycle Containment
- 25. Containment purge Supply Verify valves are Monthly
("
and Exhaust isolation Valves locked closed
- 26. Reactor Trip Breakers
- a. Verify independent Monthly '"
operability of automatic shunt and undervoltage trip functions, b Verify independent Each refueling 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 o>erability Each refueling of the siunt trip shutdown functions,
- c. Verify operability Each refueling of the manual trip shutdown to undervoltage trip fuc tions.
28CiPower: Operated Rollef Vilves' ~ Operate
~
EachWefuel_iJ gi (PORVs)r
~
~
~ shutdown
~
)0RV Solenoid Air Control'.
Valves, and Air System Check
/alves (1) Required only during periods of power operation.
(2) r determination will be started when the gross activity analysis of a filtered sample indicates 210pCi/cc and will be redetermined if the primary coolant gross radioactivity of a filtered sample increases by more than 10pti/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.
Unit 1 - Amendment No. 106 page 5 of 4 March 23, 1987 Unit 2 - Amendment No. 109 I
t
' ', ' o. 6 A, e
- s, (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 ppm, this test may be waived due to operational limitations, (11) Sample to be taken af ter a minimum of 2 Efp0 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, (12)
An approximately equal number of valves shall be tested each refueling outage such that all valves will be tested within a five year period.
If any valve fails its test, an additional number of valves equal to the number originally tested shall be tested.
If any of the additional tested valves fall, all remaining valves shall be tested.
(13)' ~ Nof re'qilired if the block Olve is shut to' isolate 7a PORV L thatL'li inoperabib -
for reasons other than' excessive seat leakage.'~ '
l(14);"Lonlifapp11 cable when the overbressure'nittigationisistemiis in servicel J
l I
b Unit 1 - Amendment No, 106 page 6 of 4 March 23, 1987 Unit 2 - Amendment No, 109
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