ML021230304
| ML021230304 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/11/2002 |
| From: | Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AP-10, TRM-U2-102 | |
| Download: ML021230304 (7) | |
Text
Arkansas Nuclear One - Administrative Services Document Control Thursday, April 11, 2002 Document Update Notification COPYHOLDER NO:
TO:
TRM-U2-102 NRC ADDRESS:
OS-DOCUMENT CONTROL, WASHINGTON, D.C. 20555 DOCUMENT NO:
TITLE:
TRM-U2 TECHNICAL REQUIREMENTS MANUAL (UNIT 2)
REVISION NO:
CHANGE NO:
010 AP-1O SUBJECT-CONTROLLED DOCUMENT checked, please sign, date, and return within 5 days.
E] ANO-1 Docket 50-313 5-ANO-2 Docket 50-368 Signature Date SIGNATURE CONFIRMS UPDATE HAS BEEN MADE RETURN TO:
ATTN: DOCUMENT CONTROL ARKANSAS NUCLEAR ONE 1448 SR 333 RUSSELLVILLE, AR 72801 kol
TECHNICAL REQUIREMENTS MANUAL REVISION 10 ARKANSAS NUCLEAR ONE, UNIT NO. 2 Revise the following pages of the associated Technical Requirements Manual with the attached pages.
REMOVE PAGES Index Pages i-2 i-3 Technical Requirements Pages INSERT PAGES i-2 i -3 3.9-1 3.9-2 B 3.9-1
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3.1 REACTIVITY CONTROL SYSTEMS (Continued) 3.1.2.6 Boric Acid Makeup Pumps - Operating.............................................
3.1-7 3.1.2.7 Borated Water Sources - Shutdown.................................................
3.1-8 3.1.2.8 Borated Water Sources - Operating.................................................
3.1-10 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protective Instrumentation..................................................
3.3-1 3.3.3.3 Seismic Instrumentation...................................................................
3.3-4 3.3.3.4 Meteorological Instrumentation.........................................................
3.3-7 3.3.3.7 Chlorine Detection Systems.............................................................
3.3-10 3.3.4.1 Turbine Overspeed Protection..........................................................
3.3-11 3.9 REFUELING OPERATIONS 3.9.3 Decay Time and Spent Fuel Storage................................................
3.9-1 BASES SECTION PAGE B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.2 Boration Systems.............................................................................
B 3.1-1 B 3.3 INSTRUMENTATION B 3.3.1.1 Reactor Protective Instrumentation..................................................
B 3.3-1 B 3.3.3.3 Seismic Instrumentation...................................................................
B 3.3-1 B 3.3.3.4 Meteorological Instrumentation.........................................................
B 3.3-2 B 3.3.3.7 Chlorine Detection Systems.............................................................
B 3.3-2 B 3.3.4.1 Turbine Overspeed Protection.......................................
B 3.3-2 R~ev.
I10 i-2 ANO-2 TRM
BASES SECTION PAGE 3.9 REFUELING OPERATIONS 3.9.3 D ecay Tim e...........................................................................................
3.9-1 ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 REPORTING REQUIREMENTS 6.9.2 S pecial R eports....................................................................................
6.9-1 ANO-2 TRM M~,
4 n Vv*.IV I i-3
REFUELING OPERATIONS DECAY TIME AND SPENT FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.3 The total heat load in the SFP shall remain within the limits specified in Figure 3.9.3-1.
APPLICABILITY:
During movement of irradiated fuel between the reactor pressure vessel and the spent fuel pool.
ACTION:
With the total heat load exceeding the requirements in Figure 3.9.3-1, or with no SFP cooling pump in operation, suspend all transfer of irradiated fuel to the SFP until the limits are restored.
SURVEILLANCE REQUIREMENTS 4.9.3 The total heat load in the pool shall be determined to be less than the limits specified in Figure 3.9.3-1.
Ar.
rev. iu ANO-2 TRM 3.9-1 ANO-2 TRM Rev. 10 1
I 3.9-1
Figure 3.9.3-1 Spent Fuel Pool Cooling Capacity 55.00 50.00 45.00 Maximum Heat Load for TTwo Pump Opraio
- E 40.00 30.00 25.00 20.00 50 55 60 65 70 75 80 85 90 95 100 SW Temperature (F) r(ev. Iu ANO-2 TRM 3.9-2 ANO-2 TRM R~ev. I1U 3.9-2
3.9 REFUELING OPERATIONS TR BASES 3/4.9.3 DECAY TIME The total heat load in the SFP consists of the fuel currently stored in the pool and that to be transferred from the reactor pressure vessel. The decay time for movement of irradiated fuel assemblies to the SFP is controlled by the maximum heat load in the SFP required to maintain temperature within design limits. The parameters impacting the cooling capacity of the SFP-are the number of pumps in operation and the service water temperature. Figure 3.9.3-1 depicts the cooling capacity limits for spent fuel pool based upon these parameters.
Rev. 10 I ANO-2 TRM B 3.9-1 I
Rev. 10 1