ML18046A700
| ML18046A700 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/27/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18046A699 | List: |
| References | |
| NUDOCS 8106040556 | |
| Download: ML18046A700 (2) | |
Text
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- 3.3 EMERGENCY CORE COOLING SYSTEM (Contd)
- g.
A maximum of one high-pressure safety inje~tion pump shall be
- -------~oPrRABLE. whenever *.the *temperature of one *or more of the PCS cold 3.3.3*
legs is< 250°F.
Prior to returning to the Power.Operation Condition after every time*the plant has been placed in the Refueling Shutdown Condition, or the Cold Shutdown Condition for more than 72
- hours and testing of Specification 4.3.h has not been accom-plished in the previous 9 mon~hs, o~ prior*to returnihg the check valves in Table 4.3.l to servi~e aft~r mainte~ance, repair or replacement, the following conditions shall be met:
- a. All pressure.isolation valves listed in Table 4.3.l shall be functional as a pressure isolation devic~, except as speci-fied in 'b.
Valve leakage shall not exceed the amounts indicated.
- b.
In the event that integrity of any pressure isolation valve specificed in Ta.ble 4.. 3.l cannot be demonstrated, at least two valves Jn each high pressure 1-ine having a non-functional valve must be in and remain in; the mode corresponding to the isolatd~ condition.(l)
- c. If Specification a and b cannot be met~ an orderly shutdown shall be initiated and the.reactor shall be in hot shutdown condition wi.thin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and cold shutdown within the next
- 24 hours.
NRC Order dated Apri 1 20, 1981 3-30 Amendment No. ;{,_.
- Effective after plant is placed in Refueling Shutdown Condition for 1981 refueling.,.
Motor-operated valves shall be placed in the closed position and power supplies deenergized.
s 1oao4 oS<:><.o (Correction - May 27., 1981)
inspection techniques that have been proven practical, and the conclusions of the evaluation shall,be used as appropriate to update the inspection program.
-f; *Surveillance--of -the regenerative heat exchanger_ and primary coola11:!:
pump flywheels shall be performed as indicated in Table 4.3.2.
- g.
A surveillance program to monitor radiation induced changes in the mechanical and impact properties of the reactor vessel materials shall be maintained as described in Section 4.5.3 of the FSAR.
The specimen removal schedule shall be as ~ndicated in Table 4.3.j.
h.* Periodic leakage testing (a)', (b} on.each check valve listed in Table 4.3.l shall be accomplished prior to returning to the Power Operation Condition after every time the plant has been placed in the Refueling Shutdown Condition, or the Cold Shutdown Condition for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if such testing has not been accomplished within the previous 9 months, and prior to returning the check valves to service after maintenance, repair or replace-ment work is performed on the valves.
i.* Whenever integrfty of a pressure isolation valve listed in Table 4.3.1 cannot be demonstrated and credit is being taken for co~pliance wit~ Specification ~.3.3.b., the.integrity of the**
- rema~ning check valve in each high pressure line having a leaking valve shall. be determined and recorded daily and the position of the bther closed val~e located in that high pressure lin~ shall
'c*'"
j
~ b~ recorded d~i.ly.
NRC Order.dated Apri 1 20, 1 981 4-17
- Amendment No. ~
I
\\ *Effective after plant is placed in Refueling Shutdown Condition for 1981 refueling.
(a}To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators} if supported by computations show-ing that the method is capable of demonstrating valve compliance with the leakage criteria.
(b}Reduced pressure testing is acceptable (see footnote 5 to Table 4,3.l}.
Minimum test differential pressure shall not be less than 150 psid.
(Correction May 27, 1981}