ML20077A696

From kanterella
Revision as of 03:20, 26 April 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Proposed TS 15.3.3,stating That RCS Temps Shall Be Maintained Greater That 350 F After Placing Reactor in Hot Shutdown Condition & Removing Note to Spec 15.3.3.D.1.a, Discussing Power Supply to Train B Swps for Unit 2
ML20077A696
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 11/16/1994
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20077A693 List:
References
NUDOCS 9411250142
Download: ML20077A696 (2)


Text

r the requirements of 15.3.3.A.1 within the time specified, the reactor shall be placed in the hot shutdown condition ylth}iilsix}hbiips. M-the requi m t: cf 15.3.3.'.1 cec net ::tisfied withir en addit 4cn 1 iS hcurs, tThe reactor shall be maintained in a condition with reactor coolant temperatures cjreatedhanpetucer 500- and 350 F, unless one residual heat removal loop is being relied upon to provide redundancy for decay heat removal. In this case the reactor shall be maintained between 350 F and 140 F.

a. One residual heat removal pump may be out of service, provided the pump is restored to operable status within 24 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The other residual heat removal pump shall be operable,
b. One residual heat exchanger may be out of service for a period of no more than 44 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
c. Any valve in the system, required to function during accident conditions, may be inoperable provided repairs are completed within 24 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Prior to initiating repaire, all valves in the system that provide the duplicate function shall be operable.

Unit 1 - Amendment No. 138 Unit 2 - Amendment No. 142 15.3.3-2a April 16, 1993 9411250142 941116 PDR ADOCK 05000266 P POR

a Four service water pumps are operable {tpolfrom*dabh"ts'ain.*

a.

b. All necessary valves, interlocks and piping required for the functioning of the Service Water System during accident conditions are also operable.
2. During power operation, the requirements of 15.3.3.D-1 may be modified to allow one of the following components to be inoperable at any one time. If the system is not restored to meet the conditions of 15.3.3.D-1 within the time period specified, both reactors will be3 placed in the hot shutdown condition within]sii[hosksZsndlinJcold shafdowipuithinT36jh6ura. If the requiremente cf 15.2.3.D-1 are not saticfied withir cn cdditienci 'O hourc, both reacter: chall be picccd 4e--the ccid-ohut4!cun ecadition.
a. One of the four required service water pumps may be out of service provided a pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. One of the two loop headers may be out of service for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.  !
c. A valve or other passive component may be out of service provided repairs can be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.  ;

i Daels The normal procedure for starting the reactor is, first, to heat the reactor coolant to near operating temperature, by running the reactor coolant pumps.

The reactor is then made critical by withdrawing control rods and/or diluting boron in the coolant.* With this mode of start-up, the energy stored in the l reactor coolant during the approach to criticality is substantially equal to that during power operation and thereforo to be conservative most engineered safety system components and auxiliary ceoling systems, shall be fully operable.

}

During low temperature physics testo there is a negligible amount of stored energy in the reactor coolant, therefore an eccident comparable in severity to I the Design Basis Accident is not possible, and the engineered safety systems are not required.

Due4e9-the-Unk-2-1494-cefueling cutcge, enc teel-n S ccrv+ec uctcr pump opecabimp-with-powee-euppl-icd by th ?.lteenate Shutdcu- Cyctc~, SOS /SO9 '. 80 vel +-bueen, mcy be concideced-eperable frcr a acr ci (cffcitc) power eupplyr-umlee-t he prev icione-of--Techwical Spec i f ication IE . 2. 0.c.

Unit 1 - Amendment No. 153 15.3.3-6 september 23, 1994 Unit 2 - Amendment No. 157

.. - _ _ _ - - _ _ _ _ _ _ - _ . _ _ _ - _ - _ _ _ - _ .