05000237/LER-2006-002, Regarding Unit 2 High Pressure Coolant Injection System Declared Inoperable

Regarding Unit 2 High Pressure Coolant Injection System Declared Inoperable

ML061640350
Person / Time
Site:	Dresden
Issue date:	06/05/2006
From:	Bost D Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR # 06-0032 LER 06-002-00
Download: ML061640350 (5)

LER-2006-002, Regarding Unit 2 High Pressure Coolant Injection System Declared Inoperable

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2372006002R00 - NRC Website

text

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Exelon Generation Company, LLC www.exeloncorp.comNula 65oo North Dresden Road Morris, I L 60450-9765 1

F 07 June 5, 2006 SVPLTR # 06-0032 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit No. 2 Renewed Facility Operating License No. DRP-1 9 NRIC Docket No. 50-237

Subject:

Licensee Event Report 237/2006-002-00, "Unit 2 High Pressure Coolant Injection System Declared Inoperable" Enclosed is Licensee Event Report 237/2006-002-00, "Unit 2 High Pressure Coolant Injection System Declared Inoperable," for Dresden Nuclear Power Station, Unit 2. This event is being reported in accordance with 10 CFR 50.73(a)(2)(v)(D), "Any event or condition that could have prevented the f ulf illment of the safety function of structures or systems that are needed to mitigate the consequences of an accident."

Should you have any questions concerning this report, please contact Mr. J. Ellis, Regulatory Assurance Manager, at (815) 416-2800.

Respectfully, Danny

.Bost Site V* e President Dre den Nuclear Power Station Enclosure cc:

Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station

NRIC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)

, the NRC may digis/carater foreac blck)not conduct or sponsor, and a person is not required to respond to, the Dresden Nuclear Power Station Unit 205 0271O 4

4. TITLE Unit 2 High Pressure Coolant Injection System Declared Inoperable

5. EVENT DATE

6. IER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED SEUNILRVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEUMENTA REV MONTH DAY YEAR N/A N/A FACILITY NAME DOCKET NUMBER 04 06 2006 2006 002 -

00 06 05 2006 N/A N/A

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201 (b) 0l 20.2203(a)(3)(i) 0l 50.73(a)(2)(i)(C)

[I 50.73(a)(2)(vii) 1[1 20.2201 (d) 0 20.2203(a)(3)(ii)

[] 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) o20.2203(a)(1) 0I 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) o20.2203(a)(2)(i)

[I 50.36(c)(l )(i)(A)

El 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)

10. POWER LEVEL El20.2203(a)(2)(ii)

[I 50.36(c)(1 )(ii)(A) 0l 50.73(a)(2)(iv)(A) 0l 50.73(a)(2)(x) o20.2203(a)(2)(fii) 0 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71(a)(4) 097 20.2203(a)(2)(iv)

[I 50.46(a)(3)(ii)

[I 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 07El 20.2203(a)(2)(v) 0I 50.73(a)(2)(i)(A)

[I 50.73(a)(2)(v)(C) 0OTHER 0l 20.2203(a)(2)(vi)

El 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)

Specity In Abstract below r in NRIC (if more space is required, use additional copies of (If more space is required, use additional copies of NRC Form366A) (17)

LER 237/2003-001, "Electromatic Relief Valve (ERV) Pressure Switches Drift Greater Than Estimated," dated July 18, 2003. This LER reported a calculation error and ineffective implementation of previous corrective actions to implement an appropriate setpoint. This event and associated corrective actions are not similar to and would not have prevented this event.

G.

Component Failure Data

NA