RS-04-151, Editorial Correction to Dresden Nuclear Power Station, Units 2 and 3, Technical Specifications Page 3.5.1-1

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Editorial Correction to Dresden Nuclear Power Station, Units 2 and 3, Technical Specifications Page 3.5.1-1
ML042800171
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 10/05/2004
From: Simpson P
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-04-151, TAC MB0170, TAC MB0171, TAC MB1337, TAC MB1338, TAC MB2715, TAC MB2716
Download: ML042800171 (6)


Text

43001 RS-04-151 October 5, 2004 U . S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-1 9 and DPR-25 NRC Docket Nos. 50-237 and 50-249

Subject:

Editorial Correction to Dresden Nuclear Power Station, Units 2 and 3, Technical Specifications Page 3.5.1-1

Reference:

Letter from S . N. Bailey (U. S . NRC) to 0. D. Kingsley (Exelon Generation Company, LLC), "Issuance of Amendments (TAC Nos. M130170, M1301711, RAB1 337, 144131338, 144132715, and MB2716)," dated November 2, 2001 In the referenced letter, the NRC issued Amendment No . 188 to Facility Operating License No.

DPR-1 9 and Amendment No. 183 to Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, respectively . The license amendments revised the Technical Specifications to reflect a change in fuel vendors from Siemens Power Corporation to General Electric, and a transition to GE14 fuel.

The need for an editorial correction on Technical Specifications page 30.01 has been identified . Specifically, revised page 3.5.1-1 issued by the NRC in the referenced letter does not contain the word "(continued)" at the bottom of the page.

Exelon Generation Company, LLC is requesting that the NRC reissue Technical Specifications page 3.5.1-1 with this editorial correction incorporated . Attachment 1 to this letter provides a markup of Technical Specifications page 3.5.1-1 . Attachment 2 provides the re-typed page with the editorial correction incorporated . The correction does not alter the meaning of the requirements in the subject Technical Specification, and does not invalidate the conclusions and approval of these amendments .

October 5, 2004 U. S. Nuclear Regulatory Commission Page 2 K you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803 .

Respectfully, Patrick R. Simpson Manager - Licensing Attachments:

1 . Technical Specifications Page 3 .5.1-1 Markup

2. Re-Typed Technical Specifications Page 3.5 .1-1 cc: Regional Administrator - NRC Region III I NRC Senior Resident Inspector - Dresden Nuclear Power Station

ATTACHMENT 1 Technical Specifications Page 3.5 .1-1 Markup

ECCS -Operating 3 .5 .1 3 .5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND ISOLATION CONDENSER (IC) SYSTEM 3 .5 .1 ECCS -Operating LCO 3 .5 .1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of five relief valves shall be OPERABLE .

APPLICABILITY : MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure < 150 psig .

ACTIONS CONDITION REHIRED ACTION COMPLETION TIME A. One Low Pressure A .1 Restore LPCI pump to 30 days Coolant Injection OPERABLE status .

UPCI) pump inoperable .

B. One LPCI subsystem B .1 Restore low pressure 7 days inoperable for reasons ECCS injection/spray other than Condition subsystem to OPERABLE A. status .

101R One Core Spray subsystem inoperable .

C. One LPCI pump in each C .1 Restore one LPCI pump 7 days subsystem inoperable . to OPERABLE status .

D. Two LPCI subsystems [) .I Restore one LPCI 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable for reasons subsystem to OPERABLE other than Condition status .

C.

Dresden 2 and 3 3 .5 .1-1 Amendment No . 188/183

ATTACHMENT 2 Re-Typed Technical Specifications Page 3 .5.1-1

ECCS-Operating 3 .5 . 1 3 .5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND ISOLATION CONDENSER (IC) SYSTEM 3 .5 .1 ECCS-Operating LCO 3 .5 .1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of five relief valves shall be OPERABLE .

APPLICABILITY : MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure ! 150 psig .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Low Pressure A .1 Restore LPCI pump to 30 days Coolant Injection OPERABLE status .

(LPCW pump inoperable .

B. One LPCI subsystem B .1 Restore low pressure 7 days inoperable for reasons ECCS injection/spray other than subsystem to OPERABLE Condition A . status .

0R One Core Spray subsystem inoperable .

C. One LPCI pump in each C .1 Restore one LPCI pump 7 days subsystem inoperable . to OPERABLE status .

D. Two LPCI subsystems D .1 Restore one LPCI .1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> inoperable for reasons subsystem to OPERABLE other than status .

Condition C .

(continued)

Dresden 2 and 3 3 .5 .1-1 Amendment No . 188/183