ML071860173

Technical Specification, Issuance of Amendment No. 264 Deletion of Reference to Banked Position Withdrawal Sequence in the Technical Specifications

ML071860173
Person / Time
Site:	Peach Bottom
Issue date:	06/29/2007
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
Hughey J, NRR/DORL, 301-415-3204
Shared Package
ml071720305	List: ML071720314 ML071860173 ML071860178
References
TAC MD2310, TAC MD2311
Download: ML071860173 (8)

Text

(5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facililty.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1) Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 264 are hereby incorporated in the license. Exelon Generation Conipany shall operate the facility in accordance with the Technical Specifications.,

(3) Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plansz, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 0," submitted by letter dated October 21, 2004.

(4) Fire Protection.

The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in

,Licensed power level was revised by Amendment No. 250, dated November 22, 2002, and will be implemented following the 14" refueling outage currently scheduled for Fall 2003.

,The training and Qualification Plan and Safeguards Contingency Plan and Appendices to the Security Plan.

Page 3 Renewed License No. DPR-56 Revised y letter dated October 28, 2004 Revised by letter dated November 5, 2004

Control Rod OPERABILITY 3.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. --------- NOTE--------- D.1 Restore compliance 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Not applicable when with the analyzed rod THERMAL POWER position sequence.

> 10% RTP.

. . . . . . . . . . . . . . . . . . . . .-- O R Two or more inoperable D.2 Restore control rod 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> control rods not in to OPERABLE status.

compliance with the analyzed rod position sequence and not separated by two or more OPERABLE control rods.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A, C, or D not met.

OR Nine or more control rods inoperable.

PBAPS UNIT 3 3.1-9 Amendment No.264

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control Lrn CB.I kU T OPERABLE: control rods shall comply with the requrements,, of, the analyzed rod position sequence.

APPLICABILITY: MODES 1 and 2 with THERMAL POWER ! 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more OPERABLE A.1 ---------NOTE--------

control rods not in Rod worth minimizer compliance with the (RWM) may be bypassed analyzed rod position as allowed by sequence. LCO 3.3.2.1, "Control Rod Block Instrumentation."

Move associated 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> control rod(s) to correct position.

OR A.2 Declare associated 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> control rod(s) inoperable.

(continued)

PBAPS UNIT 3 3.1-18 Amendment No. 264

Rod Pattern Control 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Nine or more OPERABLE 8.1 ---------NOTE---------

control rods not in RWM may be bypassed compliance with the as allowed, by analyzed rod position LCO 3.3.2.1.

sequence.

Suspend withdrawal of Immediately control rods.

AND B.2 Place the reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> mode switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with the analyzed rod position sequence.

PBAPS UNIT 3 3.1-19 Amendment No. 264

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1.1 Verify > 12 rods Immediately withdrawn.

OR C.2.1.2 Verify by Immediately administrative methods that startup with RWM inoperable has not been performed in the last calendar year.

AND C.2.2 Verify movement of During control control rods is in rod movement compliance with the analyzed rod position sequence by a second licensed operator or other qualified member of the technical staff.

D. RWM inoperable during D.1. Verify movement of During control reactor shutdown, control rods is in rod movement accordance with the analyzed rod position sequence by a second licensed operator or other qualified member of the technical staff.

(continued)

PBAPS UNIT 3 3.3-17 Amendment No. 264

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2a1a5 ------------------ NOTE-------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.2.1.6 Verify the RWM is not bypassed when 24 months THERMAL POWER is

• 10% RTP.

SR 3.3.2.1.7 ------------------ NOTE-----------------

Not required to be performed until I hour after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.2.1.8 Verify control rod sequences input to the Prior to RWM are in conformance with the analyzed declaring RWM rod position sequence. OPERABLE following loading of sequence into RWM PBAPS UNIT 3 3.3-20 Amendment No.264

Control Rod Testing-Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing-Operating LC 3 .1 .7 The requi rements of LCO 3.1.6, "Rod Pattern Control , " ay L

-na~ Uef suspended to allow performance of SDM demonstrations, control rod scram time testing, control rod friction testing, and the Startup Test Program, provided:

a. The analyzed rod position sequence requirements of SR 3.3.2.1.8 are changed to require the control rod sequence to conform to the specified test sequence.

OR

b. The RWM is bypassed; the requirements of LCO 3.3.2.1, "Control Rod Block Instrumentation," Function 2 are suspended; and conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.

APPLICABILITY: MODES 1 and 2 with LCO 3.1.6 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Suspend performance Immediately LCO not met. of the test and exception to LCO 3.1.6.

PBAPS UNIT 3 3.10-18 Amendment No. 264

SDM Test-Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling LCO 3.!0.8 The reactor mode switch position specified in Tal 1.1 .1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a. LCO 3.3.1.1, "Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a, 2.d and 2.e of Table 3.3.1.1-1;

b. 1. LCO 3.3.2.1, "Control Rod Block Instrumentation,"

MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the analyzed rod position sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence, OR

2. Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c. Each withdrawn control rod shall be. coupled to the associated CRD;

d. All control rod withdrawals during out of sequence control rod moves shall be made in notch out mode;

e. No other CORE ALTERATIONS are in progress; and

f. CRD charging water header pressure Ž 940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

PBAPS UNIT 3 3.10-20 Amendment No.264