ML033360701

Technical Specifications, Reactor Coolant System Pressure and Temperature Limits

ML033360701
Person / Time
Site:	Dresden
Issue date:	11/26/2003
From:	NRC/NRR/DLPM
To:
Banerjee M, NRR/ADPT, 415-2277
Shared Package
ML033380009	List: ML033210419 ML033360701
References
TAC MB7850, TAC MB7851
Download: ML033360701 (5)

Text

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- 3a-

a. Surveillance Requirement 4.1.A.2 - RPS Logic System Functional Test

b. Surveillance Requirement 4.1 .A.2 - Primary & Secondary Containment Logic System Functional Test

c. Surveillance Requirement 4.2.J.2 - Feedwater Pump trip Logic System Functional Test

d. Surveillance Requirement 4.6.F.1 .b - Relief Value Logic System Functional Test

e. Surveillance Requirement 4.9.A.9 - Simultaneous Diesel Generator Start

f. Surveillance Requirement 4.9.A.10 - Diesel Storage Tank Cleaning (Unit 3 and Unit 2/3 only)

Each of the above Surveillance Requirements shall be successfully demonstrated prior to entering into MODE 2 on the first plant startup following the fifteenth refueling outage (D2R15).

(7) Additional Conditions The Additional Conditions contained inAppendix B, as revised through Amendment No. 163, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.

(8) Deleted (9) Fuel Burmup The maximum rod average burnup for any rod shall be limited to 60 GWD/MTU until the completion of an NRC environmental assessment supporting an increased limit.

Amendment Nos. 205, 197

K. Deleted.

L. Deleted. [Amdt. 87, 7-24-86]

M. Deleted. [Amdt. 85, 12-12-85]

N. By Amendment No. 144, the license is amended to allow, on a one time temporary basis, operation of Dresden, Unit 3, with the corner room structural steel members in the Low Pressure Coolant Injection Corner Rooms outside the Undated Final Safety Analysis Report (UFSAR) design parameters. Operation under these conditions is allowed up to and including the next scheduled refueling outage (D3R14).

The repairs to Dresden, Unit 3, corner room structural steel shall restore the steel design margins to the current UFSAR (updated through Revision A) design criteria. The design of the modifications to the Dresden, Unit 3, comer room structural steel members will be based on use of elastic section modules and the structural steel stresses will be limited to 1.6 of the American Institute of Steel Construction (AISC allowables). The modifications to Dresden, Unit 3, comer room structural steel will be implemented during the upcoming D3R14 refueling outage.

During this interim period of operation, should vibratory ground motion exceeding the UFSAR Opeating Basis Earthquake (OBE) design parameters, Dresden, Unit 3, will be shut down for inspection and will not start up without prior NRC approval.

0. Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 158, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.

P. Deleted Q. Fuel Burnup The maximum rod average burnup for any rod shall be limited to 60 CWD/MTU until the completion of an NRC environmental assessment supporting an increased limit.

R. Exelon Generation Company, LLC shall provide the Director of the Office of Nuclear Reactor Regulation, a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company, LLC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Company, LLC's consolidated net utility plant, as recorded on Exelon Generation Company, LLC's books of account.

Amendment Nos. 205, 197

RCS PT Limits 3.4.9 1400 1300 1200 1100 c 1000 us w

L- 900 0

I-w 3800 HEATUP/COOLDOWN RATE OF COOLANT A1 s 20 0F/HR o 700 t

Ix 600 Z

I.-

I 510 en 400 a.

300 200 UPPER VESSEL AND BELTLINE LIMITS 100

---

BOTTOM HEAD CURVE 0

0 25 50 75 100 125 150 175 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)

Figure 3.4.9-1 (Page 1 of 1)

Non-Nuclear Inservice Leak and Hydrostatic Testing Curve (Valid to 32 EFPY)

Dresden 2 and 3 3.4 .9-6 Amendment No. 205, 197

RCS P/T Limits 3.4.9 1400 1300 1200 1100 CD CL1000 li

a. 900 0

I-

-J U'

) 800 0

U' HEATUPICOOLDOWN n

a: RATE OF COOLANT 2 700 < 1 00 °FIHR C,

U a: 600 z

=i 500 a:

Vn 400 U'

300 UPPER VESSEL AND BELTLINE 200 LIMITS BOTTOM HEAD 100 CURVE 0

0 25 50 75 100 125 150 175 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE (eF)

Figure 3.4.9-2 (Page 1 of 1)

Non-Nuclear Heatup/Cooldown Curve (Valid to 32 EFPY)

Dresden 2 and 3 3.4.9-7 Amendment No. 205, 197

RCS PT Limits 3.4.9 1400 1300 1200 1100

.0 n9 1000 IL 900 0

-j U'

o 700 HEATUP/COOLDOWN 0

F- RATE OF COOLANT

< 100FIHR a: 600 z

2

> 500 wIr u) 400 a:

CL 300 200 BELTLINE AND 100 NON-BELTLINE LIMITS 0

0 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (0F)

Figure 3.4.9-3 (Page 1 of 1)

Critical Operations Curve (Valid to 32 EFPY)

Dresden 2 and 3 3.4.9 -8 Amendment No. 205, 197