ML021230304

Technical Requirements Manual, Revision No. 10, Change No. AP-10, for Arkansas Nuclear One Unit 2

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: TRM-U2-102 TO: NRC ADDRESS: OS-DOCUMENT CONTROL, WASHINGTON, D.C. 20555 DOCUMENTNO: TRM-U2 TITLE: TECHNICAL REQUIREMENTS MANUAL (UNIT 2)

REVISION NO: 010 CHANGE NO: 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 with the Revise the following pages of the associated Technical Requirements Manual attached pages.

REMOVE PAGES INSERT PAGES Index Pages i-2 i-2 --

-.-. i -3 i-3 Technical Requirements Pages 3.9-1 --

3.9-2 -

B 3.9-1 -

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3.1 REACTIVITY CONTROL SYSTEMS (Continued) 3.1-7 3.1.2.6 Boric Acid Makeup Pumps - Operating .............................................

3.1-8 3.1.2.7 Borated Water Sources - Shutdown .................................................

3.1-10 3.1.2.8 Borated Water Sources - Operating .................................................

3.3 INSTRUMENTATION 3.3-1 3.3.1.1 Reactor Protective Instrumentation ..................................................

3.3-4 3.3.3.3 Seismic Instrumentation ...................................................................

3.3-7 3.3.3.4 Meteorological Instrumentation .........................................................

3.3-10 3.3.3.7 Chlorine Detection Systems .............................................................

3.3-11 3.3.4.1 Turbine Overspeed Protection ..........................................................

3.9 REFUELING OPERATIONS 3.9-1 3.9.3 Decay Time and Spent Fuel Storage ................................................

BASES PAGE SECTION B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1-1 B 3.1.2 Boration Systems .............................................................................

B 3.3 INSTRUMENTATION Reactor Protective Instrumentation .................................................. B 3.3-1 B 3.3.1.1 Seismic Instrumentation ................................................................... B 3.3-1 B 3.3.3.3 Meteorological Instrumentation ......................................................... B 3.3-2 B 3.3.3.4 Chlorine Detection Systems ............................................................. B 3.3-2 B 3.3.3.7 Turbine Overspeed Protection ....................................... ................... B 3.3-2 B 3.3.4.1 i-2 R~ev. I10 ANO-2 TRM

BASES PAGE SECTION 3.9 REFUELING OPERATIONS 3.9-1 3.9.3 D ecay Tim e ...........................................................................................

ADMINISTRATIVE CONTROLS PAGE SECTION 6.9 REPORTING REQUIREMENTS 6.9-1 6.9.2 S pecial R eports ....................................................................................

M~, 4n Vv*.IV I ANO-2 TRM i-3

REFUELING OPERATIONS DECAY TIME AND SPENT FUEL STORAGE LIMITING CONDITION FOR OPERATION Figure 3.9.3-1.

3.9.3 The total heat load in the SFP shall remain within the limits specified in APPLICABILITY: During movement of irradiated fuel between the reactor pressure vessel and the spent fuel pool.

ACTION:

no SFP cooling With the total heat load exceeding the requirements in Figure 3.9.3-1, or with fuel to the SFP until the limits are pump in operation, suspend all transfer of irradiated 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.

3.9-1 rev. iu Ar. I ANO-2 TRM 3.9-1 Rev. 10 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 60 65 70 75 80 85 90 95 100 50 55 SW Temperature (F) 3.9-2 r(ev. Iu ANO-2 TRM TRM 3.9-2 R~ev. I1U

3.9 REFUELING OPERATIONS TR BASES 3/4.9.3 DECAY TIME pool and that to be The total heat load in the SFP consists of the fuel currently stored in the time for movement of irradiated fuel transferred from the reactor pressure vessel. The decay the SFP required to maintain assemblies to the SFP is controlled by the maximum heat load in the SFP-are cooling capacity of temperature within design limits. The parameters impacting the Figure 3.9.3-1 depicts the number of pumps in operation and the service water temperature.

parameters.

the cooling capacity limits for spent fuel pool based upon these Rev. 10 II ANO-2 TRM B 3.9-1 Rev. 10 1